Annotation Property: skos:definition
http://www.w3.org/2004/02/skos/core#definition
Annotations (3)
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rdfs:isDefinedBy http://www.w3.org/2004/02/skos/core
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rdfs:label "definition" (en)
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skos:definition "A statement or formal explanation of the meaning of a concept." (en)
Superproperties (1)
Usage (1064)
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AnnotationProperty: skos:definition
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id1skos:definition "The 'activity' value of 'special form radioactive material' which is listed in <br/>
Table I or derived in Section IV4 and is used to determine the 'activity' 'limits' for <br/>the 'requirements' of [the Transport] Regulations. (From Ref. [2].)<br/>
'A ' is the maximum 'activity' of 'special form radioactive material' that can be <br/>
'1'<br/>
transported in a 'Type A package'. Fractions and multiples of 'A ' are also used <br/>
'1'<br/>
as criteria for other 'package' types, etc.<br/>The corresponding value for any other form of 'radioactive material' is 'A '.<br/>
'2'<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id10skos:definition "1. Any unintended 'event', including operating errors, equipment 'failures'<br/>
and other mishaps, the consequences or potential consequences of which are <br/>not negligible from the point of view of 'protection 'or 'safety'.<br/>
<i><b>accident conditions.</b></i> See 'plant states'.<br/>
<i><b>beyond design basis accident.</b></i> See 'plant states'.<br/>
<i><b>criticality accident.</b></i> An 'accident' involving 'criticality'.<br/>
Typically, in a 'facility' in which 'fissile material' is used.<br/>
<i><b>design basis accident.</b></i> See 'plant states'.<br/>
<i><b>nuclear accident.</b></i> [Any 'accident' involving 'facilities 'or' activities' from <br/>which a release of 'radioactive material' occurs or is likely to occur and <br/>which has resulted or may result in an international transboundary <br/>release that could be of radiological 'safety' significance for another State.] <br/>(From Ref. [6].)<br/>
<b>!</b> This is not explicitly stated to be a definition of 'nuclear accident', but it is <br/>
derived from the statement of the scope of application in Article 1 of the <br/>Convention on Early Notification of a Nuclear Accident. However, this <br/>Convention has a limited scope of application, and it is unreasonable to <br/>consider a 'nuclear accident' to be only an accident that results or may result in <br/>an international transboundary release.<br/>
<i><b>severe accident.</b></i> See 'plant states'.<br/>
2. See 'event' and 'INES'.<br/>
There remains a fundamental mismatch between the terminology used in <br/>'safety standards' and that used in 'INES'. In short, 'events' that would be <br/>considered accidents according to the 'safety standards' definition may be <br/>accidents or ‘'incidents'’ (i.e. not accidents) in 'INES' terminology. See 'INES' for <br/>a more extensive discussion.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id100skos:definition "See 'clearance' (2).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id101skos:definition "In a nuclear power plant, an instance of severely abnormal plant <br/>
behaviour caused by an abrupt transition from one plant status to another <br/>following a small 'deviation' in a plant parameter, and thus a sudden large <br/>variation in plant conditions in response to a small variation in an input.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id102skos:definition "1. Administrative and technical actions directed at a 'repository' at the end <br/>
of its 'operating lifetime' — e.g. covering of the disposed 'waste' (for a <i>near surface <br/>repository</i>) or backfilling and/or sealing (for a 'geological repository' and the <br/>passages leading to it) — and the termination and completion of 'activities' in <br/>any associated 'structures'.<br/>
For other 'facilities', the term 'decommissioning' is used.<br/>
2. [The completion of all 'operations' at some time after the emplacement <br/>
of 'spent fuel' or 'radioactive waste' in a 'disposal facility'. This includes the final <br/>engineering or other work required to bring the 'facility' to a condition that will <br/>be safe in the long term.] (From Ref. [5].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id103skos:definition "Gamma 'radiation' from radionuclides in an airborne plume.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id104skos:definition "A feature of 'protection system' 'design' such that two or more overlapping <br/>
or simultaneous output signals from several 'channels' are necessary in order to <br/>produce a 'protective action' signal by the 'logic'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id105skos:definition "See 'dose concepts'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id106skos:definition "See 'dose quantities'.<br/>
7 The terms 'siting', 'design', 'construction', 'commissioning', 'operation' and <br/>
'decommissioning' are normally used to delineate the six major stages of the lifetime of <br/>an 'authorized facility' and of the associated 'licensing' 'process'. In the special case of <i>waste <br/>disposal</i> 'facilities', 'decommissioning' is replaced in this sequence by 'closure'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id107skos:definition "The 'process' by means of which 'systems' and 'components' of 'facilities and '<br/>
'activities', having been constructed, are made operational and verified to be in <br/>accordance with the 'design' and to have met the 'required' performance criteria.<br/>
'Commissioning' may include both non-nuclear and/or non-radioactive and <br/>nuclear and/or 'radioactive' testing.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id108skos:definition "1. See 'dose concepts'.<br/>
2. See 'dose' (2).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id109skos:definition "See 'dose quantities'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id11skos:definition "See 'plant states'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id110skos:definition "See 'dose quantities'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id111skos:definition "See 'failure'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id112skos:definition "See 'failure'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id113skos:definition "[Any national or international 'regulatory body' or authority designated or <br/>
otherwise recognized as such for any purpose in connection with [the <br/>Transport] Regulations.] (From Ref. [2].)<br/>
<b>!</b> This term should be used only with reference to the Transport Regulations. <br/>
Otherwise, the more general term 'regulatory body' should be used.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id114skos:definition "A systematic programme of measures applied by a 'competent authority'<br/>
which is aimed at ensuring that the provisions of [the Transport] Regulations <br/>are met in practice. (From Ref. [2].)<br/>
The term may be used in a variety of contexts with essentially the same <br/>meaning, but often without explicit definition.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id115skos:definition "See' structures, systems and components 'and' core components'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id116skos:definition "See 'model'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id117skos:definition "See 'validation' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id118skos:definition "See 'verification' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id119skos:definition "See 'model'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id12skos:definition "See 'plant states'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id120skos:definition "See 'maintenance: predictive maintenance'.<br/>
See 'maintenance: predictive maintenance'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id121skos:definition "See 'indicator'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id122skos:definition "See 'monitoring' (2).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id123skos:definition "The upper bound for the conditional probability that a particular type of <br/>
'event' will cause unacceptable radiological consequences.<br/>
The term is used in the detailed 'event' 'screening' 'process' for 'site evaluation'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id124skos:definition "See 'risk' (3).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id125skos:definition "See 'waste management, radioactive' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id126skos:definition "The 'process' of identifying and documenting the characteristics of a <br/>
'facility'’s 'structures, systems and components' (including computer 'systems' and <br/>software), and of ensuring that changes to these characteristics are properly <br/>developed, assessed, approved, issued, implemented, verified, recorded and <br/>incorporated into the 'facility' documentation.<br/>
‘Configuration’ is used in the sense of the physical, functional and operational <br/>characteristics of the 'structures, systems and components' and parts of a 'facility'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id127skos:definition "Prevention or 'control' of releases of 'radioactive material' to the <br/>
environment in 'operation' or in 'accidents'.<br/>
'Confinement' is closely related in meaning to 'containment', but 'confinement' is <br/>typically used to refer to the 'safety function' of preventing the ‘escape’ of <br/>'radioactive material', whereas 'containment' refers to the means for achieving <br/>that function.<br/>
<b>!</b> The Transport Regulations adopt a different distinction between 'confinement'<br/>
and 'containment', namely that 'confinement' relates to preventing criticality and <br/>'containment' to preventing releases (see 'confinement system' and <i>containment <br/>system</i>).<br/>The main issue here is the differences in usage between 'nuclear safety' and <br/>'transport' 'safety'. Both terms, 'containment' and 'confinement', are used in both <br/>areas (in the Transport Regulations, in the form of 'confinement system' and <br/>'containment system'), and the usages of 'containment' are (it seems) <br/>conceptually consistent, but the usages of 'confinement' are not. <i>Confinement<br/></i>in 'nuclear safety' is the 'safety function' that is performed by 'containment'. A <br/>'confinement system' as defined in the Transport Regulations has the primary <br/>function of controlling 'criticality' (as compared with the 'containment system', <br/>the function of which is to prevent leakage of 'radioactive material'). <br/>Discussions with experts in the field have confirmed that a distinct term is <br/>needed to describe this distinct concept, and that 'confinement' is the term that <br/>has become established, but have failed to reveal any compelling reasons for <br/>the choice of that particular word.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id128skos:definition "The assembly of 'fissile material' and 'packaging' 'components' specified by <br/>
the designer and agreed to by the 'competent authority' as intended to preserve <br/>criticality 'safety'. (From Ref. [2].)<br/>
<b>!</b> This usage is specific to the Transport Regulations. See 'confinement' for more <br/>
general usage.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id129skos:definition "See 'assessment' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id13skos:definition "See 'INES'.<br/>
See 'INES'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id130skos:definition "Any person, organization or government which receives a 'consignment'. <br/>
(From Ref. [2].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id131skos:definition "Any 'package' or 'packages', or load of 'radioactive material', presented by a <br/>
'consignor' for 'transport'. (From Ref. [2].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id132skos:definition "Any person, organization or government which prepares a 'consignment'<br/>
for 'transport'. (From Ref. [2].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id133skos:definition "The 'process' of manufacturing and assembling the 'components' of a 'facility', <br/>
the carrying out of civil works, the installation of 'components' and equipment <br/>and the performance of associated tests.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id134skos:definition "Device such as a smoke detector, luminous dial or ion generating tube <br/>
that contains a small amount of 'radioactive substances'. (From Ref. [1].)<br/>
More generally, an item readily available to 'members of the public' without <br/>any 'requirements' being imposed related to any 'radiation source' therein.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id135skos:definition "The vessel into which the 'waste form' is placed for handling, 'transport', <br/>
'storage' and/or eventual 'disposal'; also the outer 'barrier' protecting the <i>waste<br/></i>from external intrusions. The 'waste container' is a 'component' of the <i>waste <br/>package</i>. For example, molten 'high level waste' glass would be poured into a <br/>specially designed 'container' ('canister'), where it would cool and solidify.<br/>
<b>!</b> Note that the term <i><b>waste canister</b></i> is considered to be a specific term for a <br/>
'container' for 'spent fuel' or vitrified 'high level waste'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id136skos:definition "Methods or physical 'structures' designed to prevent or 'control' the release <br/>
and the 'dispersion' of 'radioactive substances'.<br/>
Although related to 'confinement', 'containment' is normally used to refer to <br/>methods or 'structures' that perform a 'confinement' function, namely <br/>preventing or controlling the release of 'radioactive substances' and their <br/>'dispersion' in the environment. See 'confinement' for a more extensive <br/>discussion.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id137skos:definition "The assembly of 'components' of the 'packaging' specified by the designer as <br/>
intended to retain the 'radioactive material' during 'transport'. (From Ref. [2].)<br/>
Unlike 'confinement system', this term is consistent with the general <i>safety<br/></i>usage of 'containment'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id138skos:definition "1.' Radioactive substances' on surfaces, or within solids, liquids or gases <br/>
(including the human body), where their presence is unintended or <br/>undesirable, or the 'process' giving rise to their presence in such places.<br/>
Also used less formally to refer to a quantity, namely the 'activity' on a surface <br/>(or on a unit area of a surface).<br/>'Contamination' does not include residual 'radioactive material' remaining at a <br/>site after the completion of 'decommissioning'.<br/>
<b>!</b> The <br/>
term <br/>
'contamination' may have a connotation that is not intended. The <br/>
term 'contamination' refers only to the presence of 'radioactivity', and gives no <br/>indication of the magnitude of the hazard involved. <br/>
2. The presence of a 'radioactive substance' on a surface in quantities in <br/>
excess of 0.4 Bq/cm2 for beta and gamma emitters and <i>low toxicity alpha <br/>emitters</i>, or 0.04 Bq/cm2 for all other alpha emitters. (From Ref. [2].)<br/>
This is a regulatory definition of 'contamination', specific to the Transport <br/>Regulations. Levels below 0.4 <br/>
Bq/cm2 or 0.04 <br/>
Bq/cm2 would still be <br/>
considered 'contamination' according to the scientific definition (1).<br/>
<i><b>fixed contamination.</b></i> 'Contamination' other than 'non-fixed contamination'. <br/>(From Ref. [2].)<br/>
<i><b>non-fixed contamination.</b></i> 'Contamination' that can be removed from a <br/>surface during routine conditions of 'transport'. (From Ref. [2].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id139skos:definition "A zone in which special protective measures are necessary, owing to <br/>
actual or potential air 'contamination' or loose surface 'contamination' in excess <br/>of a specified level.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id14skos:definition "See 'INES'.<br/>
See 'INES'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id140skos:definition "1. The function or power or (usually as 'controls') means of directing, <br/>
regulating or restraining.<br/>
It should be noted that the usual meaning of the English word 'control' in <i>safety<br/></i>related contexts is somewhat ‘stronger’ (more active) than that of its usual <br/>translations and other similar words in some other languages. For example, <br/>‘'control'’ typically implies not only checking or 'monitoring' something but also <br/>ensuring that corrective or 'enforcement' measures are taken if the results of <br/>the checking or 'monitoring' indicate such a need. This is in contrast, for <br/>example, to the more limited usage of the equivalent word in French and <br/>Spanish.<br/>
<i><b>institutional control.</b></i> 'Control' of a 'radioactive' 'waste' site by an authority <br/>or institution designated under the laws of a State. This 'control' may be <br/>active ('monitoring', surveillance, remedial work) or passive (land use <br/>'control') and may be a factor in the 'design' of a 'nuclear facility' (e.g. <i>near <br/>surface repository</i>).<br/>
Most commonly used to describe 'controls' over a 'repository' after 'closure' or a <br/>'facility' undergoing 'decommissioning'.<br/>Also refers to the 'controls' placed on a site that has been released from <br/>'regulatory control' under the condition of observing specified restrictions on <br/>its future use to ensure that these restrictions are complied with.<br/>
The term 'institutional control' is more general than 'regulatory control' (i.e. <br/>'regulatory control' may be thought of as a special form of 'institutional control'). <br/>In particular, 'institutional control' measures may be passive, they may be <br/>imposed for reasons not related to 'protection' or 'safety' (although they may <br/>nevertheless have some impact on 'protection and safety'), they may be applied <br/>by organizations that do not meet the definition of a 'regulatory body', and they <br/>may apply in situations which do not fall within the scope of <i>facilities and <br/>activities</i>. As a result, some form of 'institutional control' may be considered <br/>more likely to endure further into the future than 'regulatory control'.<br/>
<i><b>regulatory control.</b></i> Any form of 'control' or regulation applied to <i>facilities<br/></i>or 'activities' by a 'regulatory body' for reasons relating to <i>radiation <br/>protection </i>or to the' safety' or 'security of radioactive sources'. (From <br/>Ref. [11].) <br/>
<b>!</b> See <br/>
also <br/>
'institutional control'.<br/>
2. A standard of comparison used to check the inferences deduced from <br/>
an experiment.<br/>
In 'protection and safety', a 'control' is most commonly a sample or a group of <br/>people that has not been exposed to 'radiation' from a particular 'source'; the <br/>occurrence of particular effects in a sample or group of people that has been <br/>exposed is compared with that in the 'control' to provide some indication of the <br/>effects that may be attributable to the 'exposure'. For example, a case–<i>control<br/></i>study is a common type of epidemiological study in which the incidence of <br/>'health effects' (the ‘cases’) in a population that has been exposed to <i>radiation<br/></i>from a particular 'source' is compared with the incidence in a similar <br/>population (the ‘'control'’) that has not been exposed, to investigate whether <br/>'exposure' due to that 'source' may be causing 'health effects'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id141skos:definition "See 'area'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id142skos:definition "(a)<br/>
For 'transport' by road or rail: any 'vehicle.'<br/>
(b)<br/>
For 'transport' by water: any 'vessel', or any hold, compartment, or <i>defined <br/>deck area</i> of a 'vessel.'<br/>
(c)<br/>
For 'transport' by air: any 'aircraft'. (From Ref. [2].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id143skos:definition "The elements of a reactor core, other than 'fuel assemblies', that are used to <br/>
provide structural support of the core construction, or the tools, devices or <br/>other items that are inserted into the reactor core for core 'monitoring', flow <br/>'control' or other technological purposes and are treated as core elements.<br/>
Examples of 'core components' are 'reactivity' 'control' devices or shutdown <br/>devices, neutron 'sources', dummy 'fuel', 'fuel' channels, instrumentation, flow <br/>restrictors and 'burnable absorbers'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id144skos:definition "See 'maintenance'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id145skos:definition "See 'analysis'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id146skos:definition "An action aimed at alleviating the radiological consequences of an <br/>
'accident'.<br/>
'Countermeasures' are forms of 'intervention' They may be 'protective actions' or <br/>'remedial actions', and these more specific terms should be used where possible.<br/>
<i><b>agricultural countermeasure.</b></i> Action taken to reduce 'contamination' of <br/>food, agricultural or forestry products before they reach consumers. <br/>(From Ref. [1].)<br/>
Note that restrictions on the sale, movement or use of contaminated food, <br/>agricultural or forestry products (i.e. measures to prevent their reaching <br/>consumers) are 'countermeasures', but are not considered to be <i>agricultural <br/>countermeasures</i>.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id147skos:definition "An approach in which all the stages in the 'lifetime' of a 'facility', 'activity' or <br/>
product are taken into consideration.<br/>
For example, the 'cradle to grave approach' to the 'safety' and <i>security of <br/>radioactive sources</i>.<br/>See 'ageing management'.<br/>See 'life cycle management'.<br/>
<b>critical</b>' (adjective)'<br/>
<b>!</b> In view of the number of special meanings attached to this word, particular <br/>
care should be taken when using the adjective ‘'critical'’ in its more common <br/>English senses (i.e. to mean extremely important, or as a derivative of the <br/>verb ‘criticize’).<br/>
1. Having a 'reactivity' of zero.<br/>
Also used, more loosely, when the 'reactivity' is greater than zero. See <br/>'criticality'.<br/>
2. Relating to the highest 'doses' or 'risks' attributable to a specified 'source'.<br/>
As in, for example, 'critical group', 'critical' pathway or 'critical' radionuclide.<br/>
3. Capable of sustaining a nuclear chain reaction.<br/>
As in, for example, 'critical' mass.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id148skos:definition "An assembly containing 'fissile material' intended to sustain a controlled <br/>
fission chain reaction at a low power level, used to investigate reactor core <br/>geometry and composition.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id149skos:definition "A group of 'members of the public' which is reasonably homogeneous with <br/>
respect to its 'exposure' for a given 'radiation' 'source' and is typical of individuals <br/>receiving the highest 'effective dose' or 'equivalent dose' (as applicable) from the <br/>given 'source'. (From Ref. [1].)<br/>
The deletion from this definition of the phrase “and given 'exposure pathway'” <br/>implies that there will not be a number of 'critical groups' for a given 'source'. <br/>Some non-IAEA publications, notably those of the International Commission <br/>on Radiological Protection [12], use a definition of 'critical group' that makes <br/>no such reference to a given 'exposure pathway', implying that there is only one <br/>'critical group' for a given 'source', namely the one with the highest total <br/>'exposure' from all 'exposure pathways'. <br/>Application of the term to 'potential exposures', such as those that may occur in <br/>the future as a result of 'radioactive waste disposal', is complicated by the facts <br/>that both the 'dose' (if it occurs) and the probability of receiving the 'dose' are <br/>relevant, and that these two parameters are essentially independent of one <br/>another. Hence, a group can be homogeneous with respect to 'dose' but not <br/>'risk', and, more importantly, vice versa. A commonly adopted solution is to <br/>define a 'critical group' — often a 'hypothetical critical group' — that is <br/>
reasonably homogeneous with respect to 'risk' and is typical of those people <br/>who might be subject to the highest 'risk'.<br/>
<i><b>hypothetical critical group.</b></i> A group of hypothetical individuals which is <br/>reasonably homogeneous with respect to the 'risk' to which its members <br/>are subject from a given 'radiation source', and is representative of the <br/>individuals likely to be most at 'risk' from the given 'source'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id15skos:definition "An 'initiating' 'event' that could lead to 'accident conditions'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id150skos:definition "See 'minimum significant activity (MSA)'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id151skos:definition "The state of a nuclear chain reacting medium when the chain reaction is <br/>
just self-sustaining (or 'critical'), i.e. when the 'reactivity' is zero.<br/>
Often used, slightly more loosely, to refer to states in which the 'reactivity' is <br/>greater than zero.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id152skos:definition "See 'accident'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id153skos:definition "A number assigned to a 'package', 'overpack' or 'freight container' containing <br/>
'fissile material' which is used to provide 'control' over the accumulation of <br/>'packages', 'overpacks' or 'freight containers' containing 'fissile material'. (From <br/>Ref. [2].)<br/>
The 'procedure' for calculating the 'criticality safety index' and the restrictions <br/>on the total sum of the 'criticality safety index' in a 'freight container' or <br/>aboard a 'conveyance' are prescribed in paras 528 and 529 of the Transport <br/>Regulations [2].<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id154skos:definition "Unit of 'activity', equal to 3.7 × 1010 Bq (exactly).<br/>
Superseded by the 'becquerel (Bq)'. 'Activity' values may be given in Ci (with <br/>the equivalent in Bq in parentheses) if they are being quoted from a reference <br/>which uses that unit.<br/>Originally, the 'activity' of a gram of radium.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id155skos:definition "See 'source' (2).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id156skos:definition "<b>!</b> The appropriate terminology of 'exemption', 'clearance', etc., should be used in <br/>
'IAEA publications'.<br/>A general term used historically to describe concepts that would now be <br/>referred to by terms such as 'exemption' or 'clearance'. The term is also <br/>sometimes used to describe a related (and controversial) philosophy that <br/>'assessments' of 'collective dose' should exclude that portion delivered at very <br/>low 'individual dose rates'.<br/>The term 'de minimis' is still used in some specific contexts, such as the London <br/>Convention 1972 [13].<br/>Derived from the maxim ‘'de minimis' non curat lex’ (the law does not concern <br/>itself with trivia).<br/>
<b>decay constant, </b>'l'<br/>
For a radionuclide in a particular energy state, the quotient of d'P' by d't', <br/>
where d'P' is the probability of a given nucleus undergoing a spontaneous <br/>nuclear transition from that energy state in the time interval d't'.<br/>
'l '= d'P '= - 1 d'N '= 'A'<br/>
d't'<br/>
'N 'd't'<br/>
'N'<br/>
where 'N' is the number of nuclei of concern existing at time 't' and 'A' is the <br/>'activity'.<br/>
Unit: reciprocal second (s–1).<br/>The 'activity' is the 'decay constant' multiplied by the number of nuclei of the <br/>radionuclide present.<br/>The 'decay constant' is related to the 'radioactive half-life, T ', of the <br/>
1/2<br/>
radionuclide by the expression:<br/>
'l '= ln 2<br/>
'T'1/2<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id157skos:definition "See 'minimum significant activity (MSA)'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id158skos:definition "1. Administrative and technical actions taken to allow the removal of <br/>
some or all of the 'regulatory controls' from a 'facility' (except for a 'repository' or <br/>for certain 'nuclear facilities 'used' 'for the 'disposal' of residues from the mining <br/>and processing of 'radioactive material', which are ‘closed’ and not <br/>‘decommissioned’).<br/>
<b>!</b> 'Decommissioning' typically includes dismantling of the 'facility' (or part <br/>
thereof), but in the IAEA’s usage this need not be the case. A facility could, <br/>for example, be 'decommissioned' without dismantling and the existing <br/>'structures' subsequently put to another use (after 'decontamination').<br/>The use of the term 'decommissioning' implies that no further use of the <i>facility<br/></i>(or part thereof) for its existing purpose is foreseen.<br/>'Decommissioning' actions are taken at the end of the 'operating lifetime' of a <br/>'facility' to retire it from service with due regard for the health and 'safety' of <br/>workers and 'members of the public' and the 'protection' of the environment. <br/>Subject to national legal and regulatory 'requirements', a 'facility' (or its <br/>remaining parts) may also be considered decommissioned if it is incorporated <br/>into a new or existing 'facility', or even if the site on which it is located is still <br/>under 'regulatory control' or 'institutional control'.<br/>The actions will need to be such as to ensure the long term 'protection' of the <br/>public and the environment, and typically include reducing the levels of residual <br/>radionuclides in the materials and on the site of the 'facility' so that the materials <br/>can be safely recycled, reused or disposed of as 'exempt waste' or as <i>radioactive <br/>waste</i> and the site can be released for 'unrestricted use' or otherwise reused.<br/>For a 'repository', the corresponding term is 'closure'.<br/>
2. [All steps leading to the release of a 'nuclear facility', other than a <br/>
'disposal facility', from 'regulatory control'. These steps include the 'processes' of <br/>'decontamination' and dismantling.] (From Ref. [5].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id159skos:definition "A document containing detailed information on the proposed <br/>
'decommissioning' of a 'facility'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id16skos:definition "See 'level: action level'.<br/><i><b>emergency action level (EAL).</b></i> See 'level:' 'action level'.<br/>
See 'level: action level'.<br/><i><b>emergency action level (EAL).</b></i> See 'level:' 'action level'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id160skos:definition "The complete or partial removal of 'contamination' by a deliberate <br/>
physical, chemical or biological 'process'.<br/>
This definition is intended to include a wide range of 'processes' for removing <br/>'contamination' from people, equipment and buildings, but to exclude the <br/>removal of radionuclides from within the human body or the removal of <br/>radionuclides by natural weathering or 'migration' 'processes', which are not <br/>considered to be 'decontamination'.<br/>See 'remediation'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id161skos:definition "The ratio of the 'activity' per unit area (or per unit mass or volume) before <br/>
a particular 'decontamination' technique is applied to the 'activity' per unit area <br/>(or per unit mass or volume) after application of the technique.<br/>
This ratio may be specified for a particular radionuclide or for gross 'activity'.<br/>The 'background' 'activity' may be first deducted from the 'activity' per unit area <br/>both before and after a particular 'decontamination' technique is applied.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id162skos:definition "See 'disposal' (3).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id163skos:definition "1. A hierarchical deployment of different levels of diverse equipment <br/>
and 'procedures' to prevent the escalation of <i>anticipated operational occurrences<br/></i>and to maintain the effectiveness of physical 'barriers' placed between a <br/>'radiation' 'source' or 'radioactive material' and 'workers', 'members of the public' or <br/>the environment, in 'operational states' and, for some 'barriers', in <i>accident <br/>conditions</i>.<br/>
The objectives of 'defence in depth' are:<br/>
(a) To compensate for potential human and 'component' 'failures';<br/>(b) To maintain the effectiveness of the 'barriers' by averting damage to the 'facility'<br/>
and to the 'barriers' themselves;<br/>
(c) To protect 'workers', 'members of the public' and the environment from harm in <br/>
'accident conditions' in the 'event' that these 'barriers' are not fully effective.<br/>
INSAG defines five levels of 'defence in depth':<br/>
(a) Level 1: Prevention of 'abnormal operation' and 'failures'.<br/>(b) Level 2: 'Control' of 'abnormal operation' and detection of <i>failures.<br/></i>(c) Level 3: 'Control' of 'accidents' within the <i>design basis.<br/></i>(d) Level 4: 'Control' of severe plant conditions, including prevention of 'accident'<br/>
progression and mitigation of the consequences of 'severe accidents.'<br/>
(e) Level 5: Mitigation of radiological consequences of significant releases of <br/>
'radioactive material'.<br/>
The levels of defence are sometimes grouped into three 'safety layers': <br/>hardware, software and management 'control'.<br/>In the context of 'waste disposal', the term 'multiple barriers' is used to describe <br/>a similar concept.<br/>See Ref. [14] for further information.<br/>
2. The application of more than one protective measure for a given 'safety'<br/>
objective, such that the objective is achieved even if one of the protective <br/>measures fails. (From Ref. [1].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id164skos:definition "The area of the weather deck of a 'vessel', or of a 'vehicle' deck of a roll-on/<br/>
roll-off ship or a ferry, which is allocated for the stowage of 'radioactive material'. <br/>(From Ref. [2].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id165skos:definition "A general term describing the overall trustworthiness of a 'system'; i.e. the <br/>
extent to which reliance can justifiably be placed on this 'system'. 'Reliability', <br/>'availability' and 'safety' are attributes of 'dependability'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id166skos:definition "See 'uranium'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id167skos:definition "A 'derived limit' on the 'activity concentration' in air of a specified <br/>
radionuclide, calculated such that 'Reference Man', breathing air with constant <br/>'contamination' at the 'DAC' while performing light physical activity for a <br/>working year, would receive an 'intake' corresponding to the <i>annual limit on <br/>intake</i> for the radionuclide in question.<br/>
The parameter values recommended by the International Commission on <br/>Radiological Protection for calculating 'DACs' are a breathing rate of 1.2 m3/h <br/>and a working year of 2000 h [15].<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id168skos:definition "See 'limit'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id169skos:definition "1. The 'process' and the result of developing a concept, detailed plans, <br/>
supporting calculations and specifications for a 'facility' and its parts.7<br/>
2. The description of 'special form radioactive material', 'low dispersible '<br/>
'radioactive material', 'package' or 'packaging' which enables such an item to be <br/>fully identified. The description may include specifications, engineering <br/>drawings, reports demonstrating compliance with regulatory 'requirements', and <br/>other relevant documentation. (From Ref. [2].)<br/>
This is a much more restricted definition than (1), and is specific to the <br/>Transport Regulations.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id17skos:definition "The 'process' of inducing 'radioactivity'.<br/>
Most commonly used to refer to the induction of 'radioactivity' in moderators, <br/>coolants, and structural and shielding materials, caused by irradiation with <br/>neutrons.<br/>The BSS definition — “The production of radionuclides by irradiation.” [1] — <br/>is technically adequate; however, the term ‘production’ gives a connotation <br/>that this is being done intentionally rather than, as is normally the case, <br/>incidentally.<br/>
<b>!</b> Care may be needed to avoid confusion when using the term 'activation' in its <br/>
everyday sense of bringing into action (e.g. of 'safety systems', for which <br/>‘actuation’ may be used).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id170skos:definition "The range of conditions and 'events' taken explicitly into account in the <br/>
'design' of a 'facility', according to established criteria, such that the 'facility' can <br/>withstand them without exceeding 'authorized limits' by the planned <i>operation<br/></i>of 'safety systems'.<br/>
Used as a noun, with the definition above. Also often used as an adjective, <br/>applied to specific categories of conditions or 'events' to mean ‘included in the <br/>'design basis'’; as, for example, in 'design basis accident', <i>design basis external <br/>events</i> and 'design basis' earthquake.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id171skos:definition "See 'plant states'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id172skos:definition "The 'external event(s)' or combination(s) of 'external events' considered in <br/>
the 'design basis' of all or any part of a 'facility'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id173skos:definition "A value of the annual probability for a particular type of 'event' to cause <br/>
unacceptable radiological consequences. It is the ratio between the <i>screening <br/>probability level</i> and the 'conditional probability value'.<br/>
The term is used in the detailed 'event' 'screening' 'process' for 'site evaluation'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id174skos:definition "See 'life'.<br/>
See 'life'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id175skos:definition "See 'minimum detectable activity (MDA)'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id176skos:definition "See 'minimum detectable activity (MDA)'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id177skos:definition "'Analysis' using, for key parameters, single numerical values (taken to have <br/>
a probability of 1), leading to a single value for the result.<br/>
In 'nuclear safety', for example, this implies focusing on 'accident' types, releases <br/>and consequences, without considering the probabilities of different <i>event<br/></i>sequences.<br/>Typically used with either ‘best estimate’ or ‘conservative’ values, based on <br/>expert judgement and knowledge of the phenomena being modelled.<br/>Contrasting terms: 'probabilistic analysis 'or 'stochastic analysis'. See <br/>'probabilistic analysis'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id178skos:definition "See 'health effects (of radiation)'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id179skos:definition "See 'radiation detriment'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id18skos:definition "A radionuclide produced by 'activation'.<br/>
Often used to distinguish from 'fission products'. For example, in <br/>'decommissioning waste' comprising structural materials from a 'nuclear facility', <br/>'activation products' might typically be found primarily within the matrix of the <br/>material, whereas 'fission products' are more likely to be present in the form of <br/>'contamination' on surfaces.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id180skos:definition "A departure from specified 'requirements'. See also 'INES'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id181skos:definition "See 'exposure, types of: medical exposure'.<br/>
See 'exposure, types of: medical exposure'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id182skos:definition "The movement of radionuclides relative to the medium in which they are <br/>
distributed, under the influence of a concentration gradient.<br/>
Usually used for the movement of airborne radionuclides (e.g. from <br/>'discharges' or resulting from an 'accident') relative to the air, and for movement <br/>of dissolved radionuclides (e.g. in groundwater or surface water, from <br/>'migration' following 'waste disposal', or in surface water from 'discharges') <br/>relative to the water.<br/>See also 'advection' (where the radionuclide does not move relative to the <br/>carrying medium, but moves with it) and 'dispersion'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id183skos:definition "See 'cause'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id184skos:definition "See 'disposal' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id185skos:definition "See 'dose equivalent quantities'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id186skos:definition "1. Planned and controlled release of (usually gaseous or liquid) <br/>
'radioactive material' to the environment.<br/>
Strictly, the act or 'process' of releasing the material, but also used to describe <br/>the material released.<br/>
<i><b>authorized discharge.</b></i> 'Discharge' in accordance with an 'authorization'.<br/>
<i><b>radioactive discharges.</b> Radioactive</i> substances arising from a <i>source <br/></i>within a 'practice' which are discharged as gases, aerosols, liquids or solids <br/>to the environment, generally with the purpose of dilution and 'dispersion'. <br/>(From Ref. [1].)<br/>
2. [A planned and controlled release to the environment, as a legitimate <br/>
'practice', within 'limits' authorized by the 'regulatory body', of liquid or gaseous <br/>'radioactive material' that originate from regulated 'nuclear facilities' during <br/>'normal operation'.] (From Ref. [5].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id187skos:definition "The spreading of 'radioactive material' in the environment.<br/>
In normal language synonymous with 'dispersion', but tends to be used in a <br/>general sense, not implying the involvement of any particular 'processes' or <br/>phenomena, e.g. the uncontrolled spreading of material that has escaped from <br/>'confinement,' or as a result of damage to (or the destruction of) a <i>sealed <br/>source</i>, 'special form radioactive material' or <i>low dispersible radioactive <br/>material</i>.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id188skos:definition "The spreading of radionuclides in air (<i><b>aerodynamic dispersion</b></i>) or water <br/>
(<i><b>hydrodynamic dispersion</b></i>) resulting mainly from physical 'processes' affecting <br/>the velocity of different molecules in the medium.<br/>
Often used in a more general sense combining all 'processes' (including <br/>molecular 'diffusion') that result in the spreading of a plume. The terms <br/><i><b>atmospheric dispersion</b></i> and <i><b>hydrodynamic dispersion</b></i> are used in this more <br/>general sense for plumes in air and water, respectively.<br/>In normal language synonymous with 'dispersal', but 'dispersion' is mostly used <br/>more specifically as defined above, whereas 'dispersal' is typically (though not <br/>universally) used as a more general expression.<br/>See also 'advection' and 'diffusion'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id189skos:definition "1. Emplacement of 'waste' in an appropriate 'facility' without the intention <br/>
of retrieval.<br/>
In some States, the term 'disposal' is used to include 'discharges' of effluents to <br/>the environment.<br/>In some States, the term 'disposal' is used administratively in such a way as to <br/>include, for example, incineration of 'waste' or the transfer of 'waste' between <br/>'operators'.<br/>
<b>!</b> In <br/>
'IAEA publications', 'disposal' should be used only in accordance with the <br/>
more restrictive definition given above.<br/>
<b>!</b> In many cases, the only element of this definition that is important is the <br/>
distinction between 'disposal' (with no intent to retrieve) and 'storage' (with <br/>intent to retrieve). In such cases, a definition is not necessary; the distinction <br/>can be made in the form of a footnote at the first use of the term 'disposal' or <br/>
'storage' (e.g. “The use of the term 'disposal' indicates that there is no intention <br/>to retrieve the 'waste'. If retrieval of the 'waste' at any time in the future is <br/>intended, the term 'storage' is used.”).<br/>
<b>!</b> The <br/>
term <br/>
'disposal' implies that retrieval is not intended; it does not mean that <br/>
retrieval is not possible.<br/>For 'storage' in a combined 'storage' and 'disposal' 'facility', for which a decision <br/>may be made at the time of its 'closure' whether to remove the 'waste' stored <br/>during the 'operation' of the 'storage' 'facility' or to dispose of it by encasing it in <br/>concrete, the question of intention of retrieval may be left open until the time <br/>of 'closure' of the 'facility'.<br/>Contrasted with 'storage'.<br/>
<i><b>direct disposal.</b></i> 'Disposal' of 'spent fuel' as 'waste'.<br/>
<i><b>geological disposal.</b></i> 'Disposal' in a 'geological repository'.<br/>
See also <i>repository.<br/></i>The term ‘intermediate 'disposal'’ is sometimes used for the 'disposal' of <i>low and <br/>intermediate level waste</i>, e.g. in boreholes (i.e. between <i>near surface disposal<br/></i>and 'geological disposal').<br/>
<i><b>near surface disposal.</b></i> 'Disposal', with or without engineered 'barriers', in a <br/>'near surface repository'.<br/>
<i><b>sub-seabed disposal.</b></i> 'Disposal' in a 'geological repository' in the rock <br/>underlying the seabed.<br/>
2. [The emplacement of 'spent fuel' or 'radioactive waste' in an appropriate <br/>
'facility' without the intention of retrieval.] (From Ref. [5].)<br/>
3. The act or 'process' of getting rid of 'waste', without the intention of <br/>
retrieval.<br/>
The terms 'deep sea disposal' and 'seabed disposal' do not strictly satisfy <br/>definitions (1) or (2), but are consistent with the everyday meaning of <i>disposal<br/></i>and are used as such.<br/>
<i><b>deep sea disposal.</b></i> 'Disposal' of 'waste' packaged in 'containers' on the deep <br/>ocean floor.<br/>
<b>!</b> The commonly used, but informal, term ‘sea dumping’ should not be used in <br/>
'IAEA publications'.<br/>As practised until 1982 in accordance with the 'requirements' of the London <br/>Convention 1972 [13].<br/>
<i><b>seabed disposal.</b></i> Emplacement of 'waste' packaged in suitable <i>containers<br/></i>at some depth into the sedimentary layers of the deep ocean floor.<br/>
This may be achieved by direct emplacement, or by placing the 'waste' in <br/>specially designed ‘penetrators’ which, when dropped into the sea, embed <br/>themselves in the sediment.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id19skos:definition "A 'component' whose functioning depends on an external input such as <br/>
actuation, mechanical movement or supply of power.<br/>
I.e. any 'component' that is not a 'passive component'.<br/>Examples of 'active components' are pumps, fans, relays and transistors. It is <br/>emphasized that this definition is necessarily general in nature, as is the <br/>corresponding definition of 'passive component'. Certain 'components', such as <br/>rupture discs, check valves, 'safety' valves, injectors and some solid state <br/>electronic devices, have characteristics that require special consideration <br/>before designation as an 'active' or 'passive component'.<br/>Contrasting term: 'passive component'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id190skos:definition "Synonymous with 'repository'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id191skos:definition "'Consignment' of, or arrangements for the 'consignment' of, 'radioactive '<br/>
'waste' for some specified (interim or final) destination, for example for the <br/>purpose of 'processing', 'disposal' or 'storage'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id192skos:definition "See 'source' (2).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id193skos:definition "The presence of two or more redundant 'systems' or 'components' to <br/>
perform an identified function, where the different 'systems' or 'components 'have <br/>different attributes so as to reduce the possibility of 'common cause failure', <br/>including 'common mode failure'.<br/>
Examples of such attributes are: different 'operating conditions', different <br/>working principles or different 'design' teams (which provide <i><b>functional <br/>diversity</b></i>), and different sizes of equipment, different manufacturers, and <br/>types of equipment that use different physical methods (which provide <br/><i><b>physical diversity</b></i>).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id194skos:definition "1. A measure of the energy deposited by 'radiation' in a target.<br/>
For definitions of the most important such measures, see 'dose quantities' and <br/>'dose concepts'.<br/>
2.' Absorbed dose', 'committed equivalent dose', 'committed effective dose', <br/>
'effective dose', 'equivalent dose' or 'organ dose', as indicated by the context.<br/>
<i><b>committed dose.</b></i> 'committed equivalent dose' or 'committed effective dose'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id195skos:definition "The ratio between the 'risk' or 'radiation detriment' per unit 'effective dose'<br/>
for high 'doses' and/or 'dose rates' and that for low 'doses' and 'dose rates'.<br/>
Used in the estimation of 'risk coefficients' for low 'doses' and 'dose rates' from <br/>observations and epidemiological findings at high 'doses' and 'dose rates'.<br/>Supersedes the 'dose rate effectiveness factor (DREF)'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id196skos:definition "See 'assessment' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id197skos:definition "Used by the International Commission on Radiological Protection and others <br/>as a synonym for 'dose per unit intake', but sometimes also used to describe <br/>other coefficients linking quantities or concentrations of 'activity' to 'doses' or <br/>'dose rates', such as the external 'dose rate' at a specified distance above a surface <br/>with a deposit of a specified 'activity' per unit area of a specified radionuclide. <br/>To avoid confusion, the term 'dose coefficient' should be used with care.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id198skos:definition "See 'dose concepts'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id199skos:definition "<i><b>annual dose.</b></i> The 'dose' due to 'external exposure' in a year plus the <br/>'committed' 'dose' from 'intakes' of radionuclides in that year.<br/>
The 'individual dose', unless otherwise stated.<br/>
<b>!</b> This is not, in general, the same as the 'dose' actually delivered during the year <br/>
in question, which would include 'doses' from radionuclides remaining in the <br/>body from 'intakes' in previous years, and would exclude 'doses' delivered in <br/>future years from 'intakes' of radionuclides during the year in question.<br/>
<i><b>avertable dose.</b></i> The 'dose' that could be averted if a 'countermeasure' or set <br/>of 'countermeasures' were to be applied.<br/>
<i><b>averted dose.</b></i> The 'dose' prevented by the application of a <i>countermeasure<br/></i>or set of 'countermeasures', i.e. the difference between the 'projected dose' if <br/>the 'countermeasure(s)' had not been applied and the actual 'projected dose'.<br/>
<i><b>collective dose.</b></i> The total 'radiation' 'dose' incurred by a population.<br/>
This is the sum of all of the 'individual doses' to members of the population. If <br/>the 'doses' continue for longer than a year, then the <i>annual individual doses<br/></i>must also be integrated over time. Unless otherwise specified, the time over <br/>which the 'dose' is integrated is infinite; if a finite upper limit is applied to the <br/>time integration, the 'collective dose' is described as ‘truncated’ at that time.<br/>Unless otherwise specified, the relevant 'dose' is normally the <i>effective dose<br/></i>(see 'collective effective dose' for the formal definition).<br/>Unit: man-sievert (man Sv). This is, strictly, just a 'sievert', but the unit man-<br/>sievert is used to distinguish the 'collective dose' from the 'individual dose' which <br/>a dosimeter would measure (just as, for example, ‘person-hours’ are used to <br/>measure the total effort devoted to a task, as opposed to the elapsed time that <br/>would be shown by a clock).<br/>Contrasting term: 'individual dose'.<br/>
<i><b>committed dose.</b></i> The 'lifetime dose' expected to result from an 'intake'.<br/>
This term partially supersedes 'dose commitment'.<br/>
[<i><b>dose commitment.</b></i> The total 'dose' that would eventually result from an <br/>'event' (e.g. a release of 'radioactive material'), a deliberate action or a finite <br/>portion of a 'practice'.]<br/>
More specific and precise terms such as 'committed dose' or <i>collective dose<br/></i>should be used as appropriate.<br/>
<i><b>individual dose.</b></i> The 'dose' incurred by an individual.<br/>
Contrasting term: 'collective dose'.<br/>
<i><b>lifetime dose.</b></i> The total 'dose' received by an individual during his or her <br/>lifetime.<br/>
In practice, often approximated as the sum of the 'annual doses' incurred. Since <br/>'annual doses' include 'committed doses', some parts of some of the <i>annual doses<br/></i>may not actually be delivered within the lifetime of the individual, and <br/>therefore this may overestimate the true 'lifetime dose'.<br/>For prospective 'assessments' of 'lifetime dose', a lifetime is normally interpreted <br/>as 70 years.<br/>
<i><b>projected dose.</b></i> The 'dose' that would be expected to be incurred if a <br/>specified 'countermeasure' or set of 'countermeasures' — or, in particular, no <br/>'countermeasures' — were to be taken.<br/>
<i><b>residual dose.</b></i> In a 'chronic exposure' situation, the 'dose' expected to be <br/>incurred in the future after 'intervention' has been terminated (or a <br/>decision has been taken not to intervene).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id2skos:definition "The 'activity' value of 'radioactive material', other than 'special form '<br/>
'radioactive material', which is listed in Table I or derived in Section IV4 and is <br/>used to determine the 'activity' 'limits' for the 'requirements' of these Regulations. <br/>(From Ref. [2].)<br/>
'A ' is the maximum 'activity' of any 'radioactive material' other than 'special form '<br/>
'2'<br/>
'radioactive material' that can be transported in a 'Type A package'. Fractions <br/>and multiples of 'A ' are also used as criteria for other 'package' types, etc.<br/>
'2'<br/>
The corresponding value for 'special form radioactive material' is 'A '.<br/>
'1'<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id20skos:definition "1. The quantity 'A' for an amount of radionuclide in a given energy state at <br/>
a given time, defined as:<br/>
'N'<br/>
'A'('t') = dd't'<br/>
where d'N' is the expectation value of the number of spontaneous nuclear <br/>transformations from the given energy state in the time interval d't'. (From <br/>Ref. [1].)<br/>
The rate at which nuclear transformations occur in a 'radioactive material'. The <br/>equation is sometimes given as: <br/>
'N'<br/>
'A'('t') = - dd't'<br/>
where 'N' is the number of nuclei of the radionuclide, and hence the rate of <br/>change of 'N' with time is negative. Numerically, the two forms are identical.<br/>The SI unit of activity is the reciprocal second (s–1), termed the <i>becquerel <br/></i>(Bq). (From Ref. [1].)<br/>Formerly expressed in 'curies '(Ci); 'activity' values may be given in Ci (with the <br/>equivalent in Bq in parentheses) if they are being quoted from a reference <br/>that uses Ci as the unit.<br/>
<i><b>specific activity.</b></i> Of a material, for the purposes of the Transport <br/>Regulations, the 'activity' per unit mass of the material in which the <br/>radionuclides are essentially uniformly distributed. (From Ref. [2].)<br/>Of a radionuclide, the 'activity' per unit mass of that nuclide. Of a material, <br/>the 'activity' per unit mass or volume of the material in which the <br/>radionuclides are essentially uniformly distributed.<br/>
The distinction in usage between 'specific activity' and <i><b>activity concentration</b></i> is <br/>controversial. Some regard the terms as synonymous, and may favour one or <br/>the other (as above). ISO 921 [7] distinguishes between 'specific activity' as the <br/>'activity' per unit mass and 'activity concentration' as the 'activity' per unit volume. <br/>Another common distinction is that 'specific activity' is used (usually as <i>activity<br/></i>per unit mass) with reference to a pure sample of a radionuclide or, less <br/>strictly, to cases where a radionuclide is intrinsically present in the material <br/>(e.g. carbon-14 in organic materials, uranium-235 in 'natural uranium'), even if <br/>the abundance of the radionuclide is artificially changed. In this usage, <i>activity <br/>concentration</i> (which may be 'activity' per unit mass or per unit volume) is used <br/>for any other situation (e.g. when the 'activity' is in the form of 'contamination' in <br/>or on a material).<br/>In general, the term 'activity concentration' is more widely applicable, is more <br/>self-evident in meaning, and is less likely than 'specific activity' to be confused <br/>with unrelated terms (such as ‘specified activities’). <i><b>Activity concentration</b></i> is <br/>therefore preferred to 'specific activity' for general use in 'safety' related <i>IAEA <br/>publications</i>.<br/>
2. See 'facilities and activities'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id200skos:definition "1. A prospective restriction on the 'individual' 'dose' delivered by a 'source', <br/>
which serves as an upper bound on the 'dose' in 'optimization 'of <i>protection and <br/>safety</i> for the 'source'.<br/>
<b>!</b> For <br/>
'medical exposure', 'dose constraint' levels should be interpreted as 'guidance '<br/>
'levels', except when used in optimizing the 'protection' of persons exposed for <br/>medical research purposes or of persons, other than 'workers', who assist in the <br/>care, support or comfort of exposed patients.<br/>
2. A prospective and 'source' related restriction on the 'individual' 'dose'<br/>
delivered by the 'source' which serves as a bound in the <i>optimization of <br/>protection and safety</i> of the 'source'. For 'occupational exposures', the <i>dose <br/>constraint</i> is a 'source' related value of 'individual' 'dose' used to limit the range of <br/>options considered in the 'process' of 'optimization'. For 'public exposure', the <i>dose <br/>constraint</i> is an upper bound on the 'annual doses' that <i>members of the public<br/></i>should receive from the planned 'operation' of any controlled 'source'. The <i>dose<br/></i>to which the 'dose constraint' applies is the 'annual dose' to any 'critical group', <br/>summed over all 'exposure pathways', arising from the predicted 'operation' of the <br/>controlled 'source'. The 'dose constraint' for each 'source' is intended to ensure that <br/>the sum of 'doses' to the 'critical group' from all controlled 'sources' remains within <br/>the 'dose limit'. For 'medical exposure' the 'dose constraint' levels should be <br/>interpreted as 'guidance levels', except when used in optimizing the 'protection' of <br/>persons exposed for medical research purposes or of persons, other than <br/>'workers', who assist in the care, support or comfort of exposed patients. (From <br/>Ref. [1].)<br/>
<b>!</b> This definition goes somewhat further than the International Commission on <br/>
Radiological Protection’s explanation of the 'dose constraint' concept [16].<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id201skos:definition "The assumed relationship between 'potential alpha energy exposure' and <br/>
'effective dose'.<br/>
Used to estimate 'doses' from measured or estimated 'exposure' to 'radon'.<br/>Unit: mSv per J·h/m3.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id202skos:definition "The product of the 'absorbed dose' at a point in the tissue or organ and the <br/>
appropriate 'quality factor' for the type of 'radiation' giving rise to the 'dose'.<br/>
A measure of the 'dose' to a tissue or organ designed to reflect the amount of <br/>harm caused.<br/>A quantity used by the International Commission on Radiation Units and <br/>Measurements in defining the operational quantities 'ambient dose equivalent', <br/>'directional dose equivalent' and 'personal dose equivalent' (see <i>dose equivalent <br/>quantities</i>). The quantity 'dose equivalent' has been superseded for <i>radiation <br/>protection</i> purposes by 'equivalent dose'. (From Ref. [1].)<br/>
<b>['effective dose equivalent, H '</b><b>]'.'</b> A measure of 'dose' designed to reflect the <br/>
<i><b>E</b></i><br/>
'risk' associated with the 'dose', calculated as the weighted sum of the <i>dose <br/>equivalents</i> in the different tissues of the body.<br/>
Superseded by 'effective dose'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id203skos:definition "<i><b>ambient dose equivalent, H*(d).</b></i> The 'dose equivalent' that would be <br/>produced by the corresponding aligned and expanded field in the <i>ICRU <br/>sphere</i> at a depth 'd' on the radius opposing the direction of the aligned <br/>field.<br/>
Parameter defined at a point in a 'radiation' field. Used as a directly <br/>measurable proxy (i.e. substitute) for 'effective dose' for use in 'monitoring' of <br/>'external exposure'.<br/>The recommended value of 'd' for 'strongly penetrating radiation' is 10 mm.<br/>
<i><b>directional dose equivalent, H</b></i>′<i><b>(d,</b></i><b>Ω').'</b> The 'dose equivalent' that would be <br/>produced by the corresponding expanded field in the 'ICRU sphere' at a <br/>depth 'd' on a radius in a specified direction Ω.<br/>
Parameter defined at a point in a 'radiation' field. Used as a directly <br/>measurable proxy (i.e. substitute) for 'equivalent dose' in the skin for use in <br/>'monitoring' of 'external exposure'.<br/>The recommended value of 'd' for 'weakly penetrating radiation' is 0.07 mm.<br/>
<b>['individual dose equivalent, penetrating, H (d)'</b><b>]'.'</b> See 'dose equivalent '<br/>
<i><b>p</b></i><br/>
'quantities': 'personal dose equivalent'.<br/>
<b>['individual dose equivalent, superficial, H (d)'</b><b>]'.'</b> See 'dose equivalent '<br/>
<i><b>s</b></i><br/>
'quantities': 'personal dose equivalent'.<br/>
<i><b>personal dose equivalent, H (d).</b></i> The 'dose equivalent' in soft tissue below <br/>
<i><b>p</b></i><br/>
a specified point on the body at an appropriate depth 'd'.<br/>
Parameter used in the BSS as a directly measurable proxy (i.e. substitute) for <br/>'equivalent dose' in tissues or organs or (with 'd' = 10 mm) for 'effective dose', in <br/>'individual monitoring' of 'external exposure'.<br/>The recommended values of 'd' are 10 mm for <i>strongly penetrating radiation<br/></i>and 0.07 mm for 'weakly penetrating radiation'. ‘Soft tissue’ is commonly <br/>interpreted as the 'ICRU sphere'.<br/>Recommended by the International Commission on Radiation Units and <br/>Measurements [17, 18] as a simplification of the two separate terms <br/><i><b>individual dose equivalent, penetrating, Hp(d)</b></i>, and <i><b>individual dose <br/>equivalent, superficial, Hs(d)</b></i>, defined in Ref. [19].<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id204skos:definition "See 'limit'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id205skos:definition "The 'committed effective dose' resulting from 'intake', by a specified means <br/>
(usually ingestion or inhalation), of unit 'activity' of a specified radionuclide in a <br/>specified chemical form.<br/>
Values are specified in the BSS [1] and recommended by the International <br/>Commission on Radiological Protection [20].<br/>For 'intakes', synonymous with 'dose coefficient'.<br/>Unit: Sv/Bq.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id206skos:definition "<i><b>absorbed dose, D.</b></i> The fundamental dosimetric quantity 'D', defined as:<br/>
'e'<br/>
'D '= d<br/>
d'm'<br/>
where d'e'– is the mean energy imparted by 'ionizing radiation' to matter in a <br/>volume element and d'm' is the mass of matter in the volume element. <br/>(From Ref. [1].)<br/>
The energy can be averaged over any defined volume, the average 'dose' being equal <br/>to the total energy imparted in the volume divided by the mass in the volume.<br/>'Absorbed dose' is defined at a point; for the average 'dose' in a tissue or organ, <br/>see 'organ dose'.<br/>Unit: 'gray (Gy)', equal to 1 J/kg (formerly, the 'rad' was used).<br/>
<i><b>collective effective dose, S.</b></i> The total 'effective dose' 'S' to a population, <br/>defined as:<br/>
'S '=<br/>
'E N'<br/>
 'i i'<br/>
'i'<br/>
where 'E ' is the average 'effective dose' in the population subgroup 'i' and 'N ' is the <br/>
'i'<br/>
'i'<br/>
number of individuals in the subgroup. It can also be defined by the integral:<br/>
•<br/>
d'N'<br/>
'S '=<br/>
'E'<br/>
d'E'<br/>
Ú0 d'E'<br/>
where <br/>
d'N 'd'E'<br/>
d'E'<br/>
is the number of individuals receiving an 'effective dose' between 'E' and <br/>'E' + d'E'. 8<br/>
The 'collective effective dose' 'S ' committed by an 'event', a deliberate action <br/>
k<br/>
or a finite portion of a 'practice' k is given by:<br/>
'S '= 'S t 'd't'<br/>
k<br/>
k<br/>
Ú ( )<br/>
'·'<br/>
where 'S ' is the 'collective effective dose' 'rate' at time 't' caused by 'k'. (From <br/>
k<br/>
Ref. [1].)<br/>
<i><b>committed effective dose, E</b></i><b>(</b>'t'<b>). </b>The quantity 'E'('t'), defined as:<br/>
'E'('t ') =<br/>
'w H '('t ')<br/>
 T T<br/>
T<br/>
8 Although the upper limit for the integral could in principle be infinite, in most <br/>
'assessments' of 'collective dose' the component associated with 'individual doses' or <i>dose <br/>rates</i> that are higher than the thresholds for the induction of 'deterministic effects' would <br/>be considered separately.<br/>
where 'H '(τ) is the 'committed equivalent dose' to tissue T over the <br/>
T<br/>
integration time τ' 'and 'w ' is the 'tissue weighting factor' for tissue T. When <br/>
T<br/>
τ is not specified, it will be taken to be 50 years for adults and the time to <br/>age 70 years for 'intakes' by children. (From Ref. [1].)<br/>
<i><b>committed equivalent dose, H </b></i><b>(</b>'t'<b>).</b> The quantity 'H '('t'), defined as:<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id207skos:definition "T<br/>
't'<br/>
't'<br/>
+<br/>
0<br/>
'H '('t ') =<br/>
'H '('t 'd<br/>
) 't'<br/>
T<br/>
T<br/>
Ú't'0<br/>
'·'<br/>
where 't ' is the time of 'intake', 'H '('t') is the 'equivalent dose rate' at time 't' in <br/>
0<br/>
T<br/>
organ or tissue T and τ is the time elapsed after an 'intake' of <i>radioactive <br/>substances</i>. When τ is not specified, it will be taken to be 50 years for <br/>adults and the time to age 70 years for 'intakes' by children. (From <br/>Ref. [1].)<br/>
<i><b>effective dose, E.</b></i> The quantity 'E', defined as a summation of the tissue <br/>'equivalent doses', each multiplied by the appropriate <i>tissue weighting <br/>factor</i>:<br/>
'E '=<br/>
'w H'<br/>
 T T<br/>
T<br/>
where 'H ' is the 'equivalent dose' in tissue T and 'w ' is the 'tissue weighting '<br/>
T<br/>
T<br/>
'factor' for tissue T. From the definition of 'equivalent dose', it follows that:<br/>
'E '=<br/>
'w'<br/>
'w D'<br/>
 T R T,R<br/>
T<br/>
R<br/>
where 'w ' is the 'radiation weighting factor' for 'radiation' R and 'D'<br/>
is the <br/>
R<br/>
T,R<br/>
average 'absorbed dose' in the organ or tissue T. (From Ref. [1].)<br/>
The unit of 'effective dose' is the 'sievert (Sv)', equal to 1 J/kg. The 'rem', equal to <br/>0.01 Sv, is sometimes used as a unit of 'equivalent dose' and 'effective dose'. This <br/>should not be used in 'IAEA publications', except when quoting directly from <br/>other publications, in which case the value in 'sieverts' should be added in <br/>parentheses.<br/>'Effective dose' is a measure of 'dose' designed to reflect the amount of <i>radiation <br/>detriment</i> likely to result from the 'dose'.<br/>Values of 'effective dose' from any type(s) of 'radiation' and mode(s) of <i>exposure<br/></i>can be compared directly.<br/>
<i><b>equivalent dose, H .</b></i> The quantity 'H'<br/>
, defined as:<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id208skos:definition "T,R<br/>
'H'<br/>
= 'w D'<br/>
T,R<br/>
R<br/>
T,R<br/>
where 'D'<br/>
is the 'absorbed dose' delivered by 'radiation' type R averaged <br/>
T,R<br/>
over a tissue or organ T and 'w ' is the 'radiation weighting factor' for <br/>
R<br/>
'radiation' type R. When the 'radiation' field is composed of different <br/>'radiation' types with different values of 'w ' the 'equivalent dose' is:<br/>
R<br/>
'H'<br/>
=<br/>
'w D'<br/>
(from Ref. [1])<br/>
Â<br/>
T<br/>
R<br/>
T,R<br/>
R<br/>
The unit of 'equivalent dose' is the 'sievert (Sv)', equal to 1 J/kg. The 'rem', equal <br/>to 0.01 Sv, is sometimes used as a unit of 'equivalent dose' and 'effective dose'. <br/>This should not be used in 'IAEA' 'publications', except when quoting directly <br/>from other publications, in which case the value in 'sieverts' should be added in <br/>parentheses.<br/>'Equivalent dose' is a measure of the 'dose' to a tissue or organ designed to <br/>reflect the amount of harm caused.<br/>Values of 'equivalent dose' to a specified tissue from any type(s) of <i>radiation<br/></i>can be compared directly.<br/>
<i><b>organ dose.</b></i> The mean 'absorbed' 'dose' 'D ' in a specified tissue or organ T <br/>
T<br/>
of the human body, given by:<br/>
1<br/>
'e'<br/>
'D '=<br/>
'D' d'm'<br/>
T<br/>
=<br/>
T<br/>
Ú<br/>
'm'<br/>
'm'T<br/>
'm'<br/>
T<br/>
T<br/>
where 'm ' is the mass of the tissue or organ, 'D' is the 'absorbed dose' in the <br/>
T<br/>
mass element d'm' and 'e ' is the total energy imparted.<br/>
T<br/>
Sometimes called tissue 'dose'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id209skos:definition "<b>!</b> Although <br/>
'dose rate' could, in principle, be defined over any unit of time (e.g. <br/>
an 'annual dose' is technically a 'dose rate'), in 'IAEA publications' the term <i>dose <br/>rate</i> should be used only in the context of short periods of time, e.g. 'dose' per <br/>second or 'dose' per hour.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id21skos:definition "See 'activity:' 'specific activity'.<br/>
See 'activity:' 'specific activity'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id210skos:definition "The ratio between the 'risk' per unit 'effective dose' for high 'dose rates' and <br/>
that for low 'dose rates'.<br/>
Superseded by 'dose and dose rate effectiveness factor' '(DDREF)'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id211skos:definition "See 'single failure criterion'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id212skos:definition "A 'component' such as a pump or valve that is operated by a 'prime mover'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id213skos:definition "See 'storage'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id214skos:definition "See 'health effects (of radiation)'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id215skos:definition "See 'dose quantities'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id216skos:definition "See 'dose equivalent'.<br/>
See 'dose equivalent'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id217skos:definition "See 'half-life' (2).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id218skos:definition "A non-routine situation that necessitates prompt action, primarily to <br/>
mitigate a hazard or adverse consequences for human health and 'safety', quality <br/>of life, property or the environment. This includes <i>nuclear and radiological <br/>emergencies</i> and conventional 'emergencies' such as fires, release of hazardous <br/>chemicals, storms or earthquakes. It includes situations for which prompt <br/>action is warranted to mitigate the effects of a perceived hazard. <br/>
<i><b>nuclear or radiological emergency.</b></i> An 'emergency' in which there is, or is <br/>perceived to be, a hazard due to:<br/>
(a) The energy resulting from a nuclear chain reaction or from the decay <br/>
of the products of a chain reaction; or<br/>
(b) 'Radiation' 'exposure'.<br/>
Points (a) and (b) approximately represent <i>nuclear and radiological <br/>emergencies</i>, respectively. However, this is not an exact distinction.<br/><i><b>Radiation emergency</b></i> is used in some cases when an explicit distinction in the <br/>nature of the hazard is immaterial (e.g. national 'radiation emergency' plan), <br/>and it has essentially the same meaning.<br/>
<i><b>transnational emergency.</b></i> A 'nuclear or radiological emergency' of actual, <br/>potential or perceived radiological significance for more than one State. <br/>This includes:<br/>
(1) A 'significant transboundary release' of 'radioactive material' (however, a <br/>
'transnational emergency' does not necessarily imply a <i>significant <br/>transboundary release</i> of 'radioactive material');<br/>
(2) A 'general emergency' at a 'facility' or other 'event' that could result in a <br/>
'significant transboundary release' (atmospheric or aquatic) of <br/>'radioactive material';<br/>
(3) Discovery of the loss or illicit removal of a 'dangerous source' that has <br/>
been transported across, or is suspected of having been transported <br/>across, a national border;<br/>
(4) An 'emergency' resulting in significant disruption to international trade <br/>
or travel;<br/>
(5) An 'emergency' warranting the taking of 'protective actions' for foreign <br/>
nationals or embassies in the State in which it occurs;<br/>
(6) An 'emergency' resulting or potentially resulting in 'severe deterministic '<br/>
'effects' and involving a fault and/or problem (such as in equipment or <br/>software) that could have serious implications for <i>safety<br/></i>internationally;<br/>
(7) An 'emergency' resulting in or potentially resulting in great concern <br/>
among the population of more than one State owing to the actual or <br/>perceived radiological hazard.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id219skos:definition "An action performed to mitigate the impact of an 'emergency' on human <br/>
health and 'safety', property or the environment.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id22skos:definition "The value of aerodynamic diameter5 such that 50% of the airborne <br/>
'activity' in a specified aerosol is associated with particles smaller than the <br/>'AMAD', and 50% of the 'activity' is associated with particles larger than the <br/>'AMAD'.<br/>
Used in internal dosimetry for simplification as a single ‘average’ value of <br/>aerodynamic diameter representative of the aerosol as a whole.<br/>The 'AMAD' is used for particle sizes for which deposition depends principally <br/>on inertial impaction and sedimentation (i.e. typically those greater than <br/>about 0.5 μm). For smaller particles, deposition typically depends primarily on <br/>'diffusion', and the <i><b>activity median thermodynamic diameter (AMTD)</b></i> — <br/>defined in an analogous way to the 'AMAD', but with reference to the <br/>thermodynamic diameter5 of the particles — is used.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id220skos:definition "See 'level:' 'action level'.<br/>
See 'level:' 'action level'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id221skos:definition "A set of conditions that warrant a similar immediate 'emergency response'.<br/>
This is the term used for communicating to the 'response organizations' and the <br/>public the level of response needed. The 'events' that belong to a given <br/>'emergency class' are defined by criteria specific to the installation, 'source' or <br/>'practice', which, if exceeded, indicate classification at the prescribed level. For <br/>each 'emergency class', the initial actions of the 'response organizations' are <br/>predefined.<br/>The IAEA defines three 'emergency classes', namely (in order of increasing <br/>severity) 'alert', 'site area emergency' and 'general emergency'. In alphabetical <br/>order:<br/>
<i><b>alert.</b></i> An 'event' involving an unknown or significant decrease in the level <br/>of 'protection' for the public or 'on-site' personnel.<br/>
When an 'alert' is declared, the state of readiness of the 'on-site' and <i>off-site<br/>response organizations</i> is increased and additional 'assessments' are made.<br/>
<i><b>general emergency.</b></i> An 'event' resulting in an actual release, or substantial <br/>probability of a release, requiring implementation of <i>urgent protective <br/>actions</i> 'off-site'.<br/>
This includes: (1) actual or projected damage to the reactor core or large <br/>amounts of 'spent fuel'; or (2) releases 'off-site' resulting in 'doses' exceeding <br/>'intervention levels' for 'urgent' 'protective actions' within hours.<br/>When a 'general emergency' is declared, 'urgent protective actions' are <br/>recommended immediately for the public near the 'facility'.<br/>
<i><b>site area emergency.</b></i> An 'event' resulting in a major decrease in the level of <br/>'protection' for the public or 'on-site' personnel.<br/>
This includes: (1) a major decrease in the level of 'protection' provided to the <br/>reactor core or large amounts of 'spent fuel'; or (2) conditions where any <br/>additional 'failures' could result in damage to the reactor core or 'spent fuel'; or <br/>(3) high 'doses' 'on-site'.<br/>When a 'site area emergency' is declared, preparations should be made to take <br/>'protective actions' 'off-site' and to control the 'doses' to 'on-site' personnel.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id222skos:definition "The 'process' whereby an authorized official classifies an 'emergency' in <br/>
order to declare the applicable 'emergency class'.<br/>
Upon declaration of the 'emergency class', the 'response organizations' initiate <br/>the predefined response actions for that 'emergency class'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id223skos:definition "See 'exposure, types of'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id224skos:definition "The period of time from the detection of conditions warranting an <br/>
'emergency response' until the completion of all the actions taken in anticipation <br/>of or in response to the radiological conditions expected in the first few months <br/>of the 'emergency'. This phase typically ends when the situation is under 'control', <br/>the 'off-site' radiological conditions have been characterized sufficiently well to <br/>
identify where food restrictions and 'temporary relocation' are 'required', and all <br/>'required' food restrictions and 'temporary relocations' have been implemented.<br/>
<i><b>initial phase.</b></i> The period of time from the detection of conditions that <br/>warrant the performance of response actions that must be taken promptly <br/>in order to be effective until those actions have been completed. These <br/>actions include 'mitigatory actions' by the 'operator' and <i>urgent protective <br/>actions</i> 'on the site' and 'off the site'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id225skos:definition "1. A description of the objectives, policy and concept of 'operations' for the<br/>
response to an 'emergency' and of the 'structure', authorities and responsibilities <br/>for a systematic, coordinated and effective response. The 'emergency plan' serves <br/>as the basis for the development of other plans, 'procedures' and checklists.<br/>
'Emergency plans' are prepared at several different levels: national, local and <br/>'facility'. They may include all 'activities' planned to be carried out by all relevant <br/>organizations and authorities, or may be primarily concerned with the actions <br/>to be carried out by a particular organization. The term <i><b>overall emergency <br/>plan</b></i> is sometimes used for clarification when the former meaning is intended.<br/>Details regarding the accomplishment of specific tasks outlined in an <br/>'emergency plan' are contained in 'emergency procedures'.<br/>
2. A set of 'procedures' to be implemented in the 'event' of an 'accident'. <br/>
(From Ref. [1].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id226skos:definition "The capability to take actions that will effectively mitigate the <br/>
consequences of an 'emergency' for human health and 'safety', quality of life, <br/>property and the environment.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id227skos:definition "A set of instructions describing in detail the actions to be taken by <br/>
response personnel in an 'emergency'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id228skos:definition "The performance of actions to mitigate the consequences of an 'emergency'<br/>
for human health and 'safety', quality of life, property and the environment. It may <br/>also provide a basis for the resumption of normal social and economic activity.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id229skos:definition "The integrated set of infrastructural elements necessary to provide the <br/>
capability for performing a specified function or task 'required' in response to a <br/>'nuclear or radiological emergency'. These elements may include authorities and <br/>responsibilities, organization, coordination, personnel, plans, 'procedures', <br/>'facilities', equipment or training.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id23skos:definition "See 'activity median aerodynamic diameter (AMAD)'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id230skos:definition "The local 'off-site' 'response organizations' that are generally available and <br/>
that perform 'emergency response' functions. These may include police, <br/>firefighters and rescue brigades, ambulance services and 'control' teams for <br/>hazardous materials.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id231skos:definition "A 'worker' who may be exposed in excess of occupational 'dose limits' while <br/>
performing actions to mitigate the consequences of an 'emergency' for human <br/>health and 'safety', quality of life, property and the environment.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id232skos:definition "The 'precautionary action zone' and/or the 'urgent protective action '<br/>
'planning zone'.<br/>
<i><b>precautionary action zone.</b></i> An area around a 'facility' for which <br/>'arrangements' have been made to take 'urgent' 'protective actions' in the <br/>'event' of a 'nuclear or radiological emergency' to reduce the 'risk' of <i>severe <br/>deterministic effects</i> 'off the site'. 'Protective actions' within this area are to be <br/>taken before or shortly after a release of 'radioactive material' or an <br/>'exposure' on the basis of the prevailing conditions at the 'facility'.<br/>
<i><b>urgent protective action planning zone.</b></i> An area around a 'facility' for <br/>which 'arrangements' have been made to take 'urgent' 'protective actions' in <br/>the 'event' of a 'nuclear or radiological emergency' to avert 'doses' <i>off the site<br/></i>in accordance with international 'safety standards'. <i>Protective actions<br/></i>within this area are to be taken on the basis of <i>environmental monitoring<br/></i>— or, as appropriate, the prevailing conditions at the 'facility'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id233skos:definition "A 'legal person' with recognized responsibility, commitment and duties <br/>
towards a 'worker' in his or her employment by virtue of a mutually agreed <br/>relationship. (From Ref. [1].)<br/>
<b>!</b> A self-employed person is regarded as being both an 'employer' and a 'worker'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id234skos:definition "1. The final stage of a 'process', especially the point at which an effect is <br/>
observed.<br/>
Used, somewhat loosely, to describe a range of different results or consequences. <br/>For example, the term ‘biological 'end point'’ is used to describe a 'health effect' (or <br/>a probability of that 'health effect') that could result from 'exposure'.<br/>
2. A radiological or other measure of 'protection' or 'safety' that is the <br/>
calculated result of an 'analysis' or 'assessment'.<br/>
Common 'end points' include estimates of 'dose' or 'risk', estimated frequency or <br/>probability of an 'event' or type of 'event' (such as core damage), expected <br/>number of 'health effects' in a population, predicted environmental <br/>concentrations of radionuclides, etc.<br/>
3. A predetermined criterion defining the point at which a specific task <br/>
or 'process' will be considered completed.<br/>
This usage often occurs in contexts such as 'decontamination' or 'remediation', <br/>where the 'end point' is typically the level of 'contamination' beyond which <br/>further 'decontamination' or 'remediation' is considered unnecessary. (In such a <br/>context, this criterion may also be an 'end point' in the sense of definition (2) — <br/>such criteria are often calculated on the basis of a level of 'dose' or 'risk' that is <br/>considered acceptable — but its application to the actual 'decontamination' or <br/>'remediation' 'operations' is in the sense of definition (3).)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id235skos:definition "1. The state of 'radioactive waste' in the final stage of 'radioactive waste '<br/>
'management', in which the 'waste' is passively safe and does not depend on <br/>'institutional control'.<br/>
In the context of 'radioactive waste management', the 'end state' includes both <br/>'disposal' and, if an adequate 'safety case' can be made, indefinite 'storage'.<br/>
2. A predetermined criterion defining the point at which a specific task <br/>
or 'process' is to be considered completed.<br/>
Used in relation to 'decommissioning' 'activities' as the final state of <br/>'decommissioning'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id236skos:definition "See 'fluence'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id237skos:definition "The application by a 'regulatory body' of sanctions against an 'operator', <br/>
intended to correct and, as appropriate, penalize non-compliance with <br/>conditions of an 'authorization'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id238skos:definition "See 'uranium'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id239skos:definition "'Absorbed dose' in the centre of the field at the surface of entry of 'radiation'<br/>
for a patient undergoing a radiodiagnostic examination, expressed in air and <br/>with backscatter. (From Ref. [1].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id24skos:definition "An assembly of 'prime movers' and 'driven equipment' used to accomplish <br/>
one or more 'safety tasks'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id240skos:definition "See 'monitoring' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id241skos:definition "The state of a 'radioactive' decay chain (or part thereof) where the 'activity'<br/>
of each radionuclide in the chain (or part of the chain) is the same.<br/>
This state is achieved when the parent nuclide has a much longer 'half-life' than <br/>any of the progeny, and after a time equal to several times the 'half-life' of the <br/>longest lived of the progeny. Hence, the term ‘secular equilibrium’ is also used <br/>(with secular in this context meaning ‘eventual’).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id242skos:definition "The 'activity concentration' of 'radon' or 'thoron' in 'radioactive equilibrium'<br/>
with its short lived progeny that would have the same <i>potential alpha energy<br/></i>concentration as the actual (non-equilibrium) mixture.<br/>
The 'equilibrium equivalent concentration' of 'radon' is given by<br/>
'EEC radon' = 0.104 × 'C'(218Po) + 0.514 × 'C'(214Pb) + 0.382 × 'C'(214Bi)<br/>
where 'C'('x') is the concentration of nuclide 'x' in air. 1 Bq/m3 <i>EEC radon<br/></i>corresponds to 5.56 × 10–6 mJ/m3.<br/>The 'equilibrium equivalent concentration' of 'thoron' is given by<br/>
'EEC thoron' = 0.913 × 'C'(212Pb) + 0.087 × 'C'(212Bi)<br/>
where 'C'('x') is the concentration of nuclide 'x' in air. 1 Bq/m3 <i>EEC thoron<br/></i>corresponds to 7.57 × 10–5 mJ/m3. <br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id243skos:definition "The ratio of the 'equilibrium equivalent concentration' of 'radon' to the <br/>
actual 'radon' concentration. (From Ref. [1].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id244skos:definition "See 'qualification'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id245skos:definition "See 'dose quantities'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id246skos:definition "The rapid, temporary removal of people from an area to avoid or reduce <br/>
short term 'radiation exposure' in an 'emergency'.<br/>
'Evacuation' is an 'urgent protective action' (a form of 'intervention'). If people are <br/>removed from the area for a longer period of time (more than a few months), <br/>the term 'relocation' is used.<br/>'Evacuation' may be performed as a precautionary action based on plant <br/>conditions within the 'precautionary action zone'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id247skos:definition "In the context of the reporting and 'analysis' of 'events', an 'event' is any <br/>
occurrence unintended by the 'operator', including operating error, equipment <br/>'failure' or other mishap, and deliberate action on the part of others, the <br/>consequences or potential consequences of which are not negligible from the <br/>point of view of 'protection' or 'safety.'<br/>
<b>!</b> As <br/>
with <br/>
'INES', the terminology related to the reporting and 'analysis' of 'events'<br/>
is not always consistent with the terminology used in 'safety standards', and <br/>
great care should be taken to avoid confusion. In particular, the definition of <br/>'event' given above is identical in essence to the 'safety standards' definition (1) <br/>of 'accident'. This difference derives from the fact that 'event' reporting and <br/>'analysis' is concerned directly with the question of whether an 'event' that could <br/>develop into an 'accident' with significant consequences actually does so; terms <br/>such as 'accident' are used only to describe the end result, and therefore other <br/>terms are needed to describe the earlier stages.<br/>See 'initiating event' and' initiating event: postulated initiating event'.<br/>
'Events'<br/>
(including 'anticipated'<br/>
Circumstances<br/>
'operational occurrences')<br/>
'Incidents'<br/>
'Scenarios:' <br/>
Situations<br/>
'Scenarios:' <br/>
(including 'initiating events',<br/>
postulated <br/>
(including 'operating '<br/>
hypothetical <br/>
'accident precursors' and<br/>
'incidents'<br/>
'conditions', 'accident '<br/>
situations<br/>
'near misses')<br/>
'conditions')<br/>
'Accidents' <br/>
Intentional causes E.g.' 'acute' Operational Nuclear and '<br/>
E.g.' chronic '<br/>
(unintentional (unauthorized acts: 'potential '<br/>
'states', <br/>
'radiological '<br/>
'potential '<br/>
causes)<br/>
'malicious' and non- 'exposure'<br/>
'design basis emergencies', <br/>
'exposure'<br/>
malicious) (e.g. <br/>
'accident' <br/>
'beyond design '<br/>
'sabotage', theft)<br/>
conditions<br/>
'basis accident' <br/>conditions<br/>
<b>Notes: </b>A 'scenario' is a postulated or assumed set of conditions and/or 'events'. A 'scenario'<br/>
may represent the conditions at a single point in time or a single 'event', or a time <br/>history of conditions and/or 'events'.<br/>
'Anticipated operational occurrences'; 'beyond design basis accidents'; <i>design basis <br/>accidents</i>: see 'plant states'.<br/>Attributes: these terms use the following attributes: acute and chronic; actual and <br/>postulated; unintentional and intentional causes; 'malicious' and non-malicious; <br/>'design basis accident 'and 'beyond design basis accident'; nuclear and radiological.<br/>Definitions:<br/>Circumstance(s): A fact, occurrence or condition, especially (in plural) the time, <br/>place, manner, cause, occasion, etc., or surroundings of an act or 'event'; (in plural) <br/>the external conditions that affect or might affect an action.<br/>Occurrence: The act or an instance of occurring, i.e. coming into being as an <i>event<br/></i>or 'process' at or during some time; happening. The act or an instance of existing <br/>or being encountered in some place or conditions.<br/>Situation: A set of circumstances; a state of affairs.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id248skos:definition "See 'analysis'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id249skos:definition "See 'package'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id25skos:definition "A 'component' that directly controls the motive power for 'actuated '<br/>
'equipment'.<br/>
Examples of 'actuation devices' include circuit breakers and relays that <i>control<br/></i>the distribution and use of electric power and pilot valves controlling <br/>hydraulic or pneumatic fluids.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id250skos:definition "The terms 'exception' and excepted are sometimes used to describe cases in <br/>which some of the 'requirements' or guidance in 'safety standards' are deemed <br/>not to apply. In this regard, the effect of 'exception' may be compared with <br/>those of 'exemption' and 'exclusion'. However, the terms 'exemption' and <br/>'exclusion' are necessarily linked to specific reasons for non-application, <br/>whereas 'exception' is not. This is in fact a normal usage of the English term <br/>'exception', not a specialized term. The term 'excepted package' in the Transport <br/>Regulations is an example of this usage; 'packages' may be excepted from <br/>specified 'requirements' of the Transport Regulations if they satisfy conditions <br/>specified in the Transport Regulations.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id251skos:definition "See 'risk' (3).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id252skos:definition "See 'risk' (3).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id253skos:definition "See 'exclusion'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id254skos:definition "The deliberate 'exclusion' of a particular category of 'exposure' from the <br/>
scope of an instrument of 'regulatory control' on the grounds that it is not <br/>considered amenable to 'control' through the regulatory instrument in question. <br/>Such 'exposure' is termed <i><b>excluded exposure</b></i>.<br/>
This term is most commonly applied to those 'exposures' from <i>natural sources<br/></i>that are least amenable to 'control', such as cosmic 'radiation' at the Earth’s <br/>surface, potassium-40 in the human body or 'naturally occurring radioactive '<br/>
'material' in which the 'activity concentrations' of natural radionuclides are <br/>below the relevant values given in IAEA 'safety standards'.<br/>The concept is related to those of 'clearance' (which is normally used in relation <br/>to materials) and 'exemption' (which relates to 'practices' or 'sources').<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id255skos:definition "The sole use, by a single 'consignor', of a 'conveyance' or of a 'large freight '<br/>
'container', in respect of which all initial, intermediate and final loading and <br/>unloading is carried out in accordance with the directions of the 'consignor' or <br/>'consignee'. (From Ref. [2].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id256skos:definition "See 'waste'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id257skos:definition "The determination by a 'regulatory body' that a 'source' or 'practice' need not <br/>
be subject to some or all aspects of 'regulatory control' on the basis that the <br/>'exposure' (including 'potential exposure') due to the 'source' or 'practice' is too <br/>small to warrant the application of those aspects or that this is the optimum <br/>option for 'protection' irrespective of the actual level of the 'doses' or 'risks'.<br/>
See also 'clearance' (1) and 'exclusion'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id258skos:definition "See 'level'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id259skos:definition "1. The act or condition of being subject to irradiation.<br/>
<b>!</b> 'Exposure' should not be used as a synonym for 'dose'. 'Dose' is a measure of the <br/>
effects of 'exposure'.<br/>'Exposure' can be divided into categories according to its nature and duration <br/>(see 'exposure situations') or according to the 'source' of the 'exposure', the <br/>people exposed and/or the circumstances under which they are exposed (see <br/>'exposure, types of').<br/>
<i><b>external exposure.</b></i> 'Exposure' to 'radiation' from a 'source' outside the body.<br/>
Contrasted with 'internal exposure'.<br/>
<i><b>internal exposure.</b></i> 'Exposure' to 'radiation' from a 'source' within the body.<br/>
Contrasted with 'external exposure'.<br/>
2'. 'The sum of the electrical charges of all of the ions of one sign produced <br/>
in air by X rays or gamma 'radiation' when all electrons liberated by photons in <br/>a suitably small element of volume of air are completely stopped in air, divided <br/>by the mass of the air in the volume element. <br/>
Unit: C/kg (in the past, the 'röntgen (R)' was used).<br/>
3. The time integral of the 'potential alpha energy' concentration in air, or <br/>
of the corresponding 'equilibrium equivalent concentration', to which an <br/>individual is exposed over a given period (e.g. a year).<br/>
Used in connection with 'exposure' to 'radon' and 'thoron' progeny.<br/>The SI unit is J·h/m3 for 'potential alpha energy' concentration or Bq·h/m3 for <br/>'equilibrium equivalent concentration'.<br/>
4. [“The product of the air concentration of a radionuclide to which a <br/>
person is exposed and the time of 'exposure'. More generally, when the air <br/>concentration varies with time, the time integral of the air concentration of a <br/>radionuclide to which a person is exposed, integrated over the time of <br/>'exposure'.”]<br/>
This definition, quoted verbatim from Ref. [21], reflects a loose usage of <br/>'exposure' found particularly in the context of airborne 'radon'. This usage is <br/>listed here for information, but it is discouraged.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id26skos:definition "See 'exposure situations'.<br/>
5 The aerodynamic diameter of an airborne particle is the diameter that a sphere <br/>
of unit density would need to have in order to have the same terminal velocity when <br/>settling in air as the particle of interest. The thermodynamic diameter of an airborne <br/>particle is the diameter that a sphere of unit density would need to have in order to <br/>have the same 'diffusion' coefficient in air as the particle of interest.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id260skos:definition "<i><b>diagnostic exposure.</b></i> See 'exposure, types of:' 'medical exposure'.<br/>
<i><b>emergency exposure.</b></i> 'Exposure' received in an 'emergency'. This may <br/>include unplanned 'exposures' resulting directly from the 'emergency' and <br/>planned 'exposures' to persons undertaking actions to mitigate the <br/>consequences of the 'emergency'.<br/>
'Emergency exposure' may be 'occupational exposure' or 'public exposure'.<br/>
<i><b>excluded exposure.</b></i> See 'exclusion'.<br/>
<i><b>medical exposure.</b></i> 'Exposure' incurred by patients as part of their own <br/>medical or dental diagnosis (<i><b>diagnostic exposure</b></i>) or treatment <br/>(<i><b>therapeutic exposure</b></i>); by persons, other than those occupationally <br/>exposed, knowingly while voluntarily helping in the support and comfort <br/>
of patients; and by volunteers in a programme of biomedical research <br/>involving their 'exposure'.<br/>
<i><b>occupational exposure.</b></i> All 'exposure' of 'workers' incurred in the course of <br/>their work, with the 'exception' of 'excluded exposures' and 'exposures' from <br/>exempt' practices' or 'exempt sources'.<br/>
<i><b>public exposure.</b></i> 'Exposure' incurred by 'members of the public' from <br/>'radiation' 'sources', excluding any 'occupational' or 'medical exposure' and the <br/>normal local 'natural background radiation' but including 'exposure' from <br/>'authorized' 'sources' and 'practices' and from 'intervention' situations. (From <br/>Ref. [1].)<br/>
<i><b>therapeutic exposure.</b></i> See 'exposure, types of:' 'medical exposure'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id261skos:definition "See 'assessment' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id262skos:definition "A route by which 'radiation' or radionuclides can reach humans and cause <br/>
'exposure'.<br/>
An 'exposure pathway' may be very simple, e.g. 'external exposure' from <br/>airborne radionuclides, or a more complex chain, e.g. 'internal exposure' from <br/>drinking milk from cows that ate grass contaminated with deposited <br/>radionuclides.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id263skos:definition "<i><b>acute exposure.</b></i> 'Exposure' received within a short period of time.<br/>
Normally used to refer to 'exposure' of sufficiently short duration that the <br/>resulting 'doses' can be treated as instantaneous (e.g. less than an hour).<br/>Usually contrasted with 'chronic exposure' and 'transitory exposure'.<br/>
<i><b>chronic exposure.</b></i> 'Exposure' persisting in time. (From Ref. [1].)<br/>
<b>!</b> The adjective ‘chronic’ relates only to the duration of 'exposure', and does not <br/>
imply anything about the magnitude of the 'doses' involved.<br/>Normally used to refer to 'exposures' persisting for many years as a result of <br/>long lived radionuclides in the environment. 'Exposure' that is too protracted <br/>to be described as 'acute exposure', but does not persist for many years, is <br/>sometimes described as <i><b>transitory exposure</b></i>.<br/>
The International Commission on Radiological Protection uses the term <br/><i><b>prolonged exposure</b></i> to describe the same concept as 'chronic exposure'. Both <br/>terms are contrasted with 'acute exposure' (and 'transitory exposure'; see above).<br/>
<i><b>chronic potential exposure.</b></i> 'Potential exposure', the probability of <br/>occurrence of which persists in time.<br/>
In a 'chronic potential exposure' situation, the 'exposure', if it occurs, may be <br/>'acute exposure' or 'chronic exposure'; it is the potential for the 'exposure' to occur <br/>that persists in time.<br/>This describes a situation in which, for example, long lived radionuclides are <br/>present in a place such that people would not normally be exposed to the <br/>'radiation', but where future human actions could result in 'exposure'.<br/>The term ‘potential 'chronic exposure'’ would describe a situation (as yet only <br/>hypothetical) of 'potential exposure' in which the 'exposure', if it occurred, would <br/>be 'chronic exposure'. To date, however, no particular need for this term has <br/>been identified.<br/>
<i><b>normal exposure.</b></i> 'Exposure' that is expected to occur under the normal <br/>'operating conditions' of a 'facility 'or' activity', including possible minor <br/>mishaps that can be kept under 'control', i.e. during 'normal operation' and <br/>'anticipated operational occurrences'.<br/>
<i><b>potential exposure.</b></i> 'Exposure' that is not expected to occur with certainty <br/>but that may result from an 'accident' at a 'source' or owing to an 'event' or <br/>sequence of 'events' of a probabilistic nature, including equipment <i>failures<br/></i>and operating errors. (From Ref. [1].)<br/>
Such 'events' could also include 'accidents' or future 'events' influencing the <br/>integrity of a 'repository'.<br/>
<i><b>prolonged exposure.</b></i> See 'exposure situations: chronic exposure'.<br/>
<i><b>transitory exposure.</b></i> See 'exposure situations: chronic exposure'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id264skos:definition "'Events' unconnected with the 'operation' of a 'facility' or the conduct of an <br/>
'activity' that could have an effect on the 'safety' of the 'facility' or 'activity'.<br/>
Typical examples of 'external events' for 'nuclear facilities' include earthquakes, <br/>tornadoes, tsunamis and aircraft crashes.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id265skos:definition "See 'exposure' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id266skos:definition "The area immediately surrounding a proposed 'site area' in which <br/>
population distribution and density, and land and water uses, are considered <br/>with respect to their effects on the possible implementation of <i>emergency<br/></i>measures.<br/>
Used in the context of 'siting' of 'facilities'.<br/>This is the area that would be the 'emergency zones' if the 'facility' were in place.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id267skos:definition "A general term encompassing 'nuclear facilities', uses of all 'sources' of <br/>
'ionizing radiation', all 'radioactive waste management' 'activities', 'transport' of <br/>'radioactive material' and any other 'practice' or circumstances in which people <br/>may be exposed to 'radiation' from naturally occurring or artificial 'sources'.<br/>
<i><b>Facilities</b></i> includes: 'nuclear facilities'; 'irradiation installations'; some mining and <br/>raw material processing 'facilities' such as uranium mines; <i>radioactive waste <br/>management</i> 'facilities'; and any other places where 'radioactive material' is <br/>produced, processed, used, handled, stored or disposed of — or where <br/>'radiation generators' are installed — on such a scale that consideration of <br/>'protection and safety' is 'required'.<br/><i><b>Activities</b></i> includes: the production, use, import and export of <i>radiation <br/>sources</i> for industrial, research and medical purposes; the 'transport' of <br/>'radioactive material'; the 'decommissioning' of 'facilities'; <i>radioactive waste <br/>management</i> 'activities' such as the 'discharge' of effluents; and some aspects of <br/>the 'remediation' of sites affected by residues from past 'activities'.<br/>This term is intended to provide an alternative to the terminology of <i>sources<br/></i>and 'practices' (or 'intervention') to refer to general categories of situations. For <br/>example, a 'practice' may involve many different 'facilities and/or activities', <br/>whereas the general definition (1) of 'source' is too broad in some cases: a <br/>'facility or activity' might constitute a 'source', or might involve the use of many <br/>'sources', depending upon the interpretation used.<br/>The term 'facilities and activities' is very general, and includes those for which <br/>little or no 'regulatory control' may be necessary or achievable: the more <br/>specific terms <i><b>authorized facility</b></i> and <i><b>authorized activity</b></i> should be used to <br/>distinguish those 'facilities and activities' for which any form of <i>authorization<br/></i>has been given.<br/>In the Fundamental Safety Principles (Safety Fundamentals), the term <br/>‘'facilities and activities' — existing and new — utilized for peaceful purposes’ is <br/>abbreviated for convenience to 'facilities and activities' as a general term <br/>encompassing any human activity that may cause people to be exposed to <br/>'radiation risks' arising from naturally occurring or artificial 'sources' (see <br/>Ref. [22], para. 1.9).<br/>
9 A small number of ‘catch-all’ terms — namely: 'facilities and activities'; '[mining '<br/>
'and milling]'; 'protection and safety'; and 'structures, systems and components' — are <br/>defined in the Safety Glossary. These terms may be used in exactly the form listed to <br/>describe a whole group of things without cumbersome repetition, or slight variations of <br/>the terms may be used to refer to particular subgroups. Although the definitions include <br/>an indication of the meanings of the separate elements of the terms, these are not <br/>intended to be applied rigidly: if precise reference is needed to particular items covered <br/>by the catch-all term, more precise terms should be used.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id268skos:definition "See 'facilities and activities'.<br/>
See 'facilities and activities'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id269skos:definition "Inability of a 'structure, system or component' to function within 'acceptance '<br/>
'criteria'.<br/>
<b>!</b> Note <br/>
that <br/>
the <br/>
'structure, system or component' is considered to fail when it <br/>
becomes incapable of functioning, whether or not this is needed at that time. <br/>A 'failure' in, for example, a backup 'system' may not be manifest until the <br/>'system' is called upon to function, either during testing or on 'failure' of the <br/>'system' it is backing up.<br/>
<i><b>common cause failure.</b></i> 'Failure' of two or more <i>structures, systems and <br/>components</i> due to a single specific 'event' or cause.<br/>
For example, a 'design' deficiency, a manufacturing deficiency, 'operation' and <br/>'maintenance' errors, a natural phenomenon, a human induced 'event', <br/>saturation of signals, or an unintended cascading effect from any other <br/>'operation' or 'failure' within the plant or from a change in ambient conditions.<br/>
<i><b>common mode failure.</b></i> 'Failure' of two or more<i> structures, systems and <br/>components</i> in the same manner or mode due to a single 'event' or cause.<br/>
I.e. 'common mode failure' is a type of 'common cause failure' in which the <br/>'structures, systems and components' fail in the same way.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id27skos:definition "See 'intake' (2).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id270skos:definition "The manner or state in which a 'structure, system or component' fails.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id271skos:definition "The 'geosphere' outside a 'repository', comprising the surrounding <br/>
geological strata, at a distance from the 'repository' such that, for modelling <br/>purposes, the 'repository' may be considered a single entity and the effects of <br/>individual 'waste packages' are not distinguished.<br/>
For practical purposes, this is often interpreted simply as the <i>geosphere<br/></i>beyond the 'near field'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id272skos:definition "See 'analysis'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id273skos:definition "The first members of an 'emergency service' to respond at the scene of an <br/>
'emergency'.<br/>
<b>fissile</b>' (adjective)'<br/>
Capable of undergoing fission by interaction with slow neutrons.<br/>
More restrictive than 'fissionable'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id274skos:definition "Uranium-233, uranium-235, plutonium-239, plutonium-241 or any <br/>
combination of these radionuclides. Excepted from this definition are:<br/>
(a) 'Natural uranium' or 'depleted uranium' which is unirradiated;<br/>(b) 'Natural uranium' or 'depleted uranium' which has been irradiated in <br/>
thermal reactors only. (From Ref. [2].)<br/>As with 'radioactive material', this is not a scientific definition, but one <br/>designed to serve a specific regulatory purpose.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id275skos:definition "A nucleus resulting from nuclear fission carrying kinetic energy from that <br/>
fission.<br/>
Used only in contexts where the particles themselves have kinetic energy and <br/>thus could represent a hazard, irrespective of whether the particles are <br/>'radioactive'. Otherwise, the more usual term 'fission product' is used.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id276skos:definition "A radionuclide produced by nuclear fission.<br/>
Used in contexts where the 'radiation' emitted by the radionuclide is the <br/>potential hazard.<br/>
<b>fissionable</b> '(adjective)'<br/>
Capable of undergoing fission.<br/>
cf. 'fissile'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id277skos:definition "See 'contamination' (2).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id278skos:definition "A measure of the strength of a 'radiation' field. Commonly used without <br/>qualification to mean 'particle fluence'.<br/>
<i><b>energy fluence, Ψ.</b></i> A measure of the energy density of a 'radiation' field, <br/>defined as:<br/>
Y = d'R'<br/>
d'a'<br/>
where d'R' is the 'radiation' energy incident on a sphere of cross-sectional <br/>area d'a'.<br/>
The 'energy fluence' rate <br/>
dY<br/>
d't'<br/>
is denoted by a lower case ψ.<br/>See Ref. [23].<br/>
<i><b>particle fluence, Φ.</b></i> A measure of the density of particles in a <i>radiation<br/></i>field, defined as:<br/>
F = d'N'<br/>
d'a'<br/>
where d'N' is the number of particles incident on a sphere of cross-<br/>sectional area d'a'.<br/>
The 'particle fluence' rate<br/>
dF<br/>
d't'<br/>
is denoted by a lower case φ .<br/>See Ref. [23].<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id279skos:definition "The fraction of an ingested element that is directly absorbed to body <br/>
fluids. (From Ref. [21].)<br/>
Often referred to colloquially as 'gut transfer factor' or ‘'f ' value’.<br/>
1<br/>
See also 'lung absorption type', a similar concept for 'activity' in the respiratory tract.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id28skos:definition "See 'risk projection model'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id280skos:definition "An article of 'transport' equipment designed to facilitate the 'transport' of <br/>
goods, either packaged or unpackaged, by one or more modes of <i>transport<br/></i>without intermediate reloading, which is of a permanent enclosed character, <br/>rigid and strong enough for repeated use, and must be fitted with devices <br/>facilitating its handling, particularly in transfer between 'conveyances' and from <br/>one mode of 'transport' to another. A <i><b>small freight container</b></i> is that which has <br/>either any overall outer dimension less than 1.5 m, or an internal volume of not <br/>more than 3 m3. Any other 'freight container' is considered to be a <i><b>large freight <br/>container</b></i>. (From Ref. [2].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id281skos:definition "See 'nuclear fuel'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id282skos:definition "See 'nuclear fuel'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id283skos:definition "A set of 'fuel elements' and associated 'components' which are loaded into <br/>
and subsequently removed from a reactor core as a single unit.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id284skos:definition "See 'nuclear fuel cycle'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id285skos:definition "A rod of 'nuclear fuel', its 'cladding' and any associated 'components'<br/>
necessary to form a structural entity.<br/>
Commonly referred to as <i><b>fuel rod</b></i> in light water reactors.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id286skos:definition "See 'fuel element'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id287skos:definition "See 'diversity'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id288skos:definition "See 'indicator'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id289skos:definition "Prevention of influences from the mode of 'operation' or 'failure' of one <br/>
circuit or 'system' on another.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id29skos:definition "See 'sorption'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id290skos:definition "Release, especially in a reactor core, of 'fission products' from the 'fuel' pin <br/>
gap, which occurs immediately after 'failure' of the 'fuel' cladding and is the first <br/>radiological indication of 'fuel' damage or 'fuel failure'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id291skos:definition "See 'emergency class'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id292skos:definition "See 'disposal' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id293skos:definition "See 'repository'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id294skos:definition "Those parts of the lithosphere not considered to be part of the 'biosphere'.<br/>
In 'safety assessment', usually used to distinguish the subsoil and rock (below <br/>the depth affected by normal human 'activities', in particular agriculture) from <br/>the soil that is part of the 'biosphere'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id295skos:definition "The period of time during which a 'safety function' is ensured in an 'event'<br/>
with no necessity for action by personnel.<br/>
Typical 'grace periods' range from 20 min to 12 h. The period of grace may be <br/>achieved by means of the automation of actuations, the adoption of passive <br/>'systems' or the inherent characteristics of a material (such as the heat capacity <br/>of the 'containment' 'structure'), or by any combination of these.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id296skos:definition "1. For a system of 'control', such as a regulatory system or a 'safety system', <br/>
a 'process' or method in which the stringency of the 'control' measures and <br/>conditions to be applied is commensurate, to the extent practicable, with the <br/>
likelihood and possible consequences of, and the level of 'risk' associated with, a <br/>loss of 'control'.<br/>
An example of a 'graded approach' in general would be a structured method by <br/>means of which the stringency of application of 'requirements' is varied in <br/>accordance with the circumstances, the regulatory systems used, the <br/>'management systems' used, etc. For example, a method in which:<br/>
(1) The significance and complexity of a product or service are determined;<br/>(2) The potential impacts of the product or service on health, 'safety', 'security', <br/>
the environment, and the achieving of quality and the organization’s <br/>objectives are determined;<br/>
(3) The consequences if a product fails or if a service is carried out <br/>
incorrectly are taken into account.<br/>
2. An application of 'safety requirements' that is commensurate with the <br/>
characteristics of the 'practice' or 'source' and with the magnitude and likelihood <br/>of the 'exposures'.<br/>
See also 'exclusion', 'exemption' and 'clearance' and 'optimization'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id297skos:definition "The SI unit of 'kerma' and 'absorbed dose', equal to 1 J/kg.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id298skos:definition "Gamma 'radiation' from radionuclides deposited on the ground.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id299skos:definition "See 'level'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id3skos:definition "See 'plant states:' 'anticipated operational occurrence'.<br/>
See 'plant states:' 'anticipated operational occurrence'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id30skos:definition "The movement of a substance or the transfer of heat by the motion of the <br/>
gas (usually air) or liquid (usually water) in which it is present.<br/>
Sometimes used with the more common meaning — transfer of heat by the <br/>horizontal motion of the air — but in 'IAEA publications' is more often used in <br/>a more general sense, particularly in 'safety assessment', to describe the <br/>movement of a radionuclide due to the movement of the liquid in which it is <br/>dissolved or suspended.<br/>Usually contrasted with 'diffusion', where the radionuclide moves relative to <br/>the carrying medium.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id300skos:definition "See 'level'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id301skos:definition "See 'fractional absorption in the gastrointestinal tract, f '.<br/>
See 'fractional absorption in the gastrointestinal tract, f '.<br/>
1<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id302skos:definition "See 'survey'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id303skos:definition "1. For a radionuclide, the time required for the 'activity' to decrease, by a <br/>
'radioactive' decay 'process', by half.<br/>
Where it is necessary to distinguish this from other 'half-lives' (see (2)), the <br/>term 'radioactive half-life' should be used.<br/>The 'half-life' is related to the 'decay constant, 'λ, by the expression:<br/>
2<br/>
'T'<br/>
= ln<br/>
1/ 2<br/>
'l'<br/>
2. The time taken for the quantity of a specified material (e.g. a <br/>
radionuclide) in a specified place to decrease by half as a result of any specified <br/>'process' or 'processes' that follow similar exponential patterns to 'radioactive' decay.<br/>
<i><b>biological half-life.</b></i> The time taken for the quantity of a material in a <br/>specified tissue, organ or region of the body (or any other specified biota) <br/>to halve as a result of biological 'processes'.<br/>
<i><b>effective half-life, T .</b></i> The time taken for the 'activity' of a radionuclide in <br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id304skos:definition "a specified place to halve as a result of all relevant 'processes'.<br/>
1<br/>
1<br/>
= Â<br/>
'T'<br/>
'T'<br/>
eff<br/>
i<br/>
i<br/>
where 'T ' is the 'half-life' for 'process' i.<br/>
i<br/>
<i><b>radioactive half-life.</b></i> For a radionuclide, the time required for the <i>activity<br/></i>to decrease, by a 'radioactive' decay 'process', by half.<br/>
The term <i><b>physical half-life</b></i> is also used for this concept.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id305skos:definition "<i><b>deterministic effect.</b></i> A 'health effect of radiation' for which generally a <br/>threshold level of 'dose' exists above which the severity of the effect is <br/>greater for a higher 'dose'. Such an effect is described as a 'severe '<br/>
'deterministic effect' if it is fatal or life threatening or results in a permanent <br/>injury that reduces quality of life.<br/>
The level of the threshold 'dose' is characteristic of the particular <i>health effect<br/></i>but may also depend, to a limited extent, on the exposed individual. Examples <br/>of 'deterministic effects' include erythema and acute 'radiation' syndrome <br/>('radiation' sickness).<br/>The term <i><b>non-stochastic effect</b></i> is used in some older publications, but is now <br/>superseded.<br/>Contrasting term: 'stochastic effect'.<br/>
<i><b>early effect.</b></i> A 'radiation' induced 'health effect' that occurs within months of <br/>the 'exposure' that caused it.<br/>
All 'early effects' are 'deterministic effects'; most, but not all, <i>deterministic effects<br/></i>are 'early effects'.<br/>
<i><b>hereditary effect.</b></i> A 'radiation' induced 'health effect' that occurs in a <br/>descendant of the exposed person.<br/>
The less precise term ‘genetic effect’ is also used, but 'hereditary effect' is <br/>preferred.<br/>'Hereditary effects' are usually 'stochastic effects'.<br/>Contrasting term: 'somatic effect'.<br/>
<i><b>late effect.</b></i> A 'radiation' induced 'health effect' that occurs years after the <br/>'exposure' that caused it.<br/>
The most common 'late effects' are 'stochastic effects', such as leukaemia and <br/>solid cancers, but some 'deterministic effects' (e.g. cataract formation) can also <br/>be 'late effects'.<br/>
<b>['non-stochastic effect'</b><b>]'.'</b> See 'health effects (of radiation):' <i>deterministic <br/>effect</i>.<br/>
<i><b>severe deterministic effect.</b></i> A 'deterministic effect' that is fatal or life <br/>threatening or results in a permanent injury that reduces quality of life. <br/>See 'health effects (of radiation): deterministic effect'.<br/>
<i><b>somatic effect.</b></i> A 'radiation' induced 'health effect' that occurs in the <br/>exposed person.<br/>
This includes effects occurring after birth that are attributable to 'exposure' in <br/>utero.<br/>'Deterministic effects' are normally also 'somatic effects'; 'stochastic effects' may be <br/>'somatic effects' or 'hereditary effects'.<br/>Contrasting term: 'hereditary effect'.<br/>
<i><b>stochastic effect.</b></i> A 'radiation' induced 'health effect', the probability of <br/>occurrence of which is greater for a higher 'radiation dose' and the severity <br/>of which (if it occurs) is independent of 'dose'.<br/>
'Stochastic effects' may be 'somatic effects' or 'hereditary effects', and generally <br/>occur without a threshold level of 'dose'. Examples include solid cancers and <br/>leukaemia.<br/>Contrasting term: 'deterministic effect'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id306skos:definition "An individual who has been accredited through appropriate national <br/>
'procedures' to practise a profession related to health (e.g. medicine, dentistry, <br/>chiropractic, podiatry, nursing, medical physics, 'radiation' and nuclear medical <br/>technology, radiopharmacy, occupational health). (From Ref. [1].)<br/>
Used in the BSS to distinguish from a 'medical practitioner', who satisfies <br/>additional criteria.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id307skos:definition "Medical supervision intended to ensure the initial and continuing fitness <br/>
of 'workers' for their intended tasks. (From Ref. [1].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id308skos:definition "See 'waste classes'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id309skos:definition "See 'health effects (of radiation)'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id31skos:definition "See 'dispersion'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id310skos:definition "X ray equipment and other types of 'radiation' generators capable of <br/>
operating at generating potentials above 300 kV, and radionuclide teletherapy <br/>equipment.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id311skos:definition "See 'radiation'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id312skos:definition "See 'waste classes'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id313skos:definition "See 'uranium'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id314skos:definition "Engineering in which factors that could influence human performance <br/>
are taken into account.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id315skos:definition "See 'dispersion'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id316skos:definition "See 'critical group'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id317skos:definition "An IAEA copyrighted hard copy or electronic product issued with <br/>
unlimited distribution and bearing the IAEA emblem (logo) on the front.<br/>
A document is a non-copyrighted hard copy or electronic product issued with <br/>limited distribution and bearing the IAEA emblem on the front. It may or <br/>may not be fully edited and typeset (usually not). A manuscript is an unissued <br/>copy of a draft publication or document.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id318skos:definition "A sphere of 30 cm diameter made of 'tissue equivalent material' with a <br/>
density of 1 g/cm3 and a mass composition of 76.2% oxygen, 11.1% carbon, <br/>10.1% hydrogen and 2.6% nitrogen.<br/>
Used as a reference phantom in defining 'dose equivalent quantities'.<br/>See Ref. [24].<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id319skos:definition "The term is in use but there is no agreed definition. The vague phrase is used <br/>in different contexts to mean different things.<br/>The term <i><b>nuclear trafficking</b></i> is vaguer still and more open to <br/>(mis)interpretation, and is better avoided where clear communication is <br/>necessary.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id32skos:definition "General 'process' in which characteristics of a 'structure, system or '<br/>
'component' gradually change with time or use.<br/>
Although the term 'ageing' is defined in a neutral sense — the changes <br/>involved in 'ageing' may have no effect on 'protection' or 'safety', or could even <br/>have a beneficial effect — it is most commonly used with a connotation of <br/>changes that are (or could be) detrimental to 'protection and safety' (i.e. as a <br/>synonym of 'ageing degradation').<br/>
<i><b>non-physical ageing.</b></i> The 'process' of becoming out of date (i.e. obsolete) <br/>owing to the evolution of knowledge and technology and associated <br/>changes in codes and standards.<br/>
Examples of 'non-physical ageing' effects include the lack of an effective <br/>'containment' or 'emergency' core cooling 'system', the lack of 'safety' 'design'<br/>
features (such as 'diversity', separation or 'redundancy'), the unavailability of <br/>qualified spare parts for old equipment, incompatibility between old and new <br/>equipment, and outdated 'procedures' or documentation (e.g. which thus do <br/>not comply with current regulations).<br/>Strictly, this is not always 'ageing' as defined above, because it is sometimes not <br/>due to changes in the 'structure, system or component' itself. Nevertheless, the <br/>effects on 'protection and safety', and the solutions that need to be adopted, are <br/>often very similar to those for 'physical ageing'.<br/>The term <i><b>technological obsolescence</b></i> is also used.<br/>
<i><b>physical ageing.</b></i><b> </b>'Ageing' of 'structures, systems and components' due to <br/>physical, chemical and/or biological 'processes' ('ageing' mechanisms).<br/>
Examples of 'ageing' mechanisms include wear, thermal or <i>radiation<br/></i>embrittlement, corrosion and microbiological fouling.<br/>The term <i><b>material ageing</b></i> is also used.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id320skos:definition "See 'waste management, radioactive' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id321skos:definition "See 'inspection'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id322skos:definition "Any unintended 'event', including operating errors, equipment 'failures', <br/>
'initiating events', 'accident precursors', 'near misses' or other mishaps, or <br/>unauthorized act, 'malicious' or non-malicious, the consequences or potential <br/>consequences of which are not negligible from the point of view of <i>protection<br/></i>or 'safety'.<br/>
See also 'event' and 'INES'.<br/>
<b>!</b> The <br/>
word <br/>
'incident' is often used, in 'INES' and elsewhere, to describe 'events'<br/>
that are, in effect, minor 'accidents', i.e. that are distinguished from <i>accidents<br/></i>only in terms of being less severe. This is a distinction with little basis in <br/>normal usage. An 'incident' can be minor or major, just as an 'accident' can, but <br/>unlike an 'accident', an 'incident' can be caused intentionally.<br/>This definition of 'incident' was derived on the basis of the entries for <i>accident<br/></i>and 'event' and the explanation of the term 'incident' given in Ref. [22].<br/>
<i><b>nuclear incident.</b></i> [Any occurrence or series of occurrences having the <br/>same origin which causes 'nuclear damage' or, but only with respect to <br/>'preventive measures', creates a grave and imminent threat of causing such <br/>damage.] (From Ref. [25].)<br/>
<b>!</b> This usage is specific to the Convention on Supplementary Compensation for <br/>
Nuclear Damage [25], for the purposes of the Convention, and should <br/>otherwise be avoided.<br/>
<i><b>serious incident.</b></i> See 'INES'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id323skos:definition "See 'assessment' (2).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id324skos:definition "Equipment that possesses both of the following characteristics:<br/>
(a)<br/>
The ability to perform its required function is unaffected by the <i>operation<br/></i>or 'failure' of other equipment;<br/>
(b)<br/>
The ability to perform its function is unaffected by the occurrence of the <br/>effects resulting from the 'postulated initiating event' for which it is <br/>required to function.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id325skos:definition "<i><b>condition indicator.</b></i> Characteristic of a <i>structure, system or component<br/></i>that can be observed, measured or trended to infer or directly indicate the <br/>current and future ability of the 'structure, system or component' to <br/>function within 'acceptance criteria'.<br/>
<i><b>functional indicator.</b></i> 'Condition indicator' that is a direct indication of the <br/>current ability of a 'structure, system or component' to function within <br/>'acceptance criteria'.<br/>
<i><b>performance indicator.</b></i> Characteristic of a 'process' that can be observed, <br/>measured or trended to infer or directly indicate the current and future <br/>performance of the 'process', with particular emphasis on satisfactory <br/>performance for 'safety'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id326skos:definition "See 'dose concepts'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id327skos:definition "See 'dose equivalent quantities:' 'personal dose equivalent'.<br/>
See 'dose equivalent quantities:' 'personal dose equivalent'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id328skos:definition "See 'dose equivalent quantities:' 'personal dose equivalent'.<br/>
See 'dose equivalent quantities:' 'personal dose equivalent'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id329skos:definition "See 'monitoring' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id33skos:definition "'Ageing' effects that could impair the ability of a 'structure, system or '<br/>
'component' to function within its 'acceptance criteria'.<br/>
Examples include reduction in diameter due to wear of a rotating shaft, loss in <br/>material toughness due to 'radiation' embrittlement or thermal 'ageing', and <br/>cracking of a material due to fatigue or stress corrosion cracking.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id330skos:definition "See 'package'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id331skos:definition "A simple scale, designed for promptly communicating to the public in <br/>
consistent terms the 'safety' significance of 'events' at 'nuclear facilities'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id332skos:definition "The scale should not be confused with 'emergency classification' systems, and <br/>should not be used as a basis for 'emergency response' actions.<br/>
<b>!</b> The <br/>
'INES' terminology — particularly the use of the terms 'incident' and<br/>
'accident—' is different from that used in 'safety standards', and great care <br/>should be taken to avoid confusion between the two. Unless otherwise <br/>indicated, the terms 'incident' and 'accident' are used in this Safety Glossary with <br/>their 'safety standards' meaning (see 'incident' and 'accident' (1) and under 'event').<br/>
Level 0 (<i><b>deviation</b></i>): An 'event' with no 'safety' significance.<br/>
Level 1 (<i><b>anomaly</b></i>): An 'event' beyond the authorized operating regime, <br/>but not involving significant 'failures' in 'safety' provisions, significant <br/>spread of 'contamination' or overexposure of 'workers'.<br/>
Level 2 (<i><b>incident</b></i>): [An 'event' involving significant 'failure' in <i>safety<br/></i>provisions, but with sufficient 'defence in depth' remaining to cope with <br/>additional 'failures' and/or resulting in a 'dose' to a 'worker' exceeding a <br/>statutory 'dose limit' and/or leading to the presence of 'activity' in <i>on-site<br/></i>areas not expected by 'design' and which require corrective action.]<br/>
Level 3 (<i><b>serious incident</b></i>): [A minor' accident', where only the last layer of <br/>'defence in depth' remained operational and/or involving severe spread of <br/>'contamination' 'on-site' or 'deterministic effects' to a 'worker' and/or a very <br/>small release of 'radioactive material' 'off-site' (i.e. a 'critical group dose' of <br/>the order of tenths of a millisievert).]<br/>
Level 4 (<i><b>accident without significant off-site risk</b></i>): An 'accident' involving <br/>significant damage to the installation (e.g. partial core melt) and/or <br/>overexposure of one or more 'workers' resulting in a high probability of <br/>death and/or an 'off-site' release such that the 'critical group dose' is of the <br/>order of a few millisieverts.<br/>
Level 5 (<i><b>accident with off-site risk</b></i>): An 'accident' resulting in severe <br/>damage to the installation and/or an 'off-site' release of <i>radioactive <br/>material</i> radiologically equivalent to hundreds or thousands of TBq of <br/>131I, likely to result in partial implementation of 'countermeasures' covered <br/>by 'emergency plans'.<br/>
E.g. the 1979 'accident' at Three Mile Island, USA (severe damage to the <br/>installation) or the 1957 'accident' at Windscale, UK (severe damage to the <br/>installation and significant 'off-site' release).<br/>
Level 6 (<i><b>serious accident</b></i>): An 'accident' involving a significant release of <br/>'radioactive material' and likely to require full implementation of planned <br/>'countermeasures', but less severe than a 'major accident'.<br/>
E.g. the 1957 'accident' at Kyshtym, USSR (now in the Russian Federation).<br/>
Level 7 (<i><b>major accident</b></i>): An 'accident' involving a major release of <br/>'radioactive material' with widespread health and environmental effects.<br/>
E.g. the 1986 'accident' at Chernobyl, USSR (now in Ukraine).<br/>
<i><b>incident.</b></i> [An 'event' classified as Level 1, 2 or 3, i.e. beyond the authorized <br/>operating regime, but not as serious as an 'accident'.]<br/>
<i><b>accident.</b></i> [An 'event' classified as Level 4, 5, 6 or 7, i.e. that involves a <br/>release of 'radioactive material' 'off-site' likely to cause 'public exposure' at <br/>least of the order of 'authorized limits' or requiring 'countermeasures' to be <br/>taken, or causes significant damage to the installation, or results in <br/>'exposure' of 'workers' 'on-site' to such a degree that there is a high <br/>probability of early death.]<br/>
<b>!</b> There remains a fundamental mismatch between the terminology used in <br/>
'safety standards' and that used in 'INES'. In short, 'events' that would be <br/>considered 'accidents' according to the 'safety standards' definition may be <br/>'accidents' or 'incidents' (i.e. not 'accidents') in 'INES' terminology. This is not a <br/>serious day to day technical problem because the two areas are quite separate. <br/>However, it is a potential problem for public communication.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id333skos:definition "In dosimetry, unless otherwise stated, an 'infant' is assumed to be a one year <br/>old, and annual quantities (e.g. 'annual dose', annual 'intake') relating to an <br/>'infant' refer to the year starting at birth. See also 'child' and <i>reference <br/>individual</i>.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id334skos:definition "See 'lung absorption type'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id335skos:definition "See 'emergency phase'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id336skos:definition "An identified 'event' that leads to 'anticipated operational occurrences' or <br/>
'accident conditions'.<br/>
This term (often shortened to <i><b>initiator</b></i>) is used in relation to 'event' reporting <br/>and 'analysis', i.e. when such 'events' have occurred. For the consideration of <br/>hypothetical 'events' considered at the 'design' stage, the term <i>postulated <br/>initiating event</i> is used.<br/>
<i><b>postulated initiating event (PIE).</b></i> An 'event' identified during 'design' as <br/>capable of leading to 'anticipated operational occurrences' or <i>accident <br/>conditions</i>.<br/>
The primary causes of 'postulated initiating events' may be credible equipment <br/>'failures' and 'operator' errors (both within and external to the 'facility') or human <br/>induced or natural 'events'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id337skos:definition "See 'initiating event'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id338skos:definition "An examination, observation, measurement or test undertaken to assess <br/>
'structures', 'systems and components' and materials, as well as operational <br/>'activities', technical 'processes', organizational 'processes', 'procedures' and <br/>personnel competence.<br/>
<i><b>in-service inspection.</b></i> 'Inspection' of <i>structures, systems and components<br/></i>undertaken over the 'operating lifetime' by or on behalf of the <i>operating <br/>organization</i> for the purpose of identifying age related degradation or <br/>conditions that, if not addressed, might lead to the 'failure' of <i>structures, <br/>systems or components</i>.<br/>
'Inspection' of operational 'activities', 'processes', etc., by or on behalf of the <br/>'operating organization' would normally be described by terms such as <i>self-<br/>assessment</i> and 'audit'.<br/>
<i><b>regulatory inspection.</b></i> 'Inspection' undertaken by or on behalf of the <br/>'regulatory body'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id339skos:definition "Any 'installation processing radioactive substances' for which the yearly <br/>
throughput is higher than 10 000 times the 'exemption activity' levels presented <br/>in Table I-I of the Basic Safety Standards. (From Ref. [1].)<br/>
A general term designed to include 'facilities' engaged in manufacturing <br/>'sources' or 'consumer products', or handling them in bulk as a commercial <br/>undertaking, but to exclude small scale users of such products.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id34skos:definition "Engineering, 'operations' and 'maintenance' actions to control within <br/>
'acceptable limits' the 'ageing degradation' of 'structures, systems and components'.<br/>
Examples of engineering actions include 'design', 'qualification' and 'failure analysis'. <br/>Examples of 'operations' actions include surveillance, carrying out operating <br/>'procedures' within specified 'limits' and performing environmental measurements.<br/><i><b>Life management</b></i> (or <i><b>lifetime management</b></i>) is the integration of <i>ageing <br/>management</i> with economic planning: (1) to optimize the 'operation', <br/>'maintenance' and 'service life' of 'structures, systems and components'; (2) to <br/>maintain an acceptable level of performance and 'safety'; and (3) to maximize <br/>the return on investment over the 'service life' of the 'facility'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id340skos:definition "See 'control' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id341skos:definition "1. The act or 'process' of taking radionuclides into the body by inhalation <br/>
or ingestion or through the skin. (From Ref. [1].)<br/>
2. The 'activity' of a radionuclide taken into the body in a given time <br/>
period or as a result of a given 'event'.<br/>
<i><b>acute intake.</b></i> An 'intake' occurring within a time period short enough that <br/>it can be treated as instantaneous for the purposes of assessing the <br/>resulting 'committed dose'.<br/>
<b>!</b> The <br/>
'exposure' that results from an 'acute intake' is not necessarily 'acute '<br/>
'exposure'. For a long lived radionuclide that is retained in the body, an <i>acute <br/>intake</i> will result in 'chronic exposure'.<br/>
<i><b>chronic intake.</b></i> An 'intake' over an extended period of time, such that it <br/>cannot be treated as a single instantaneous 'intake' for the purposes of <br/>assessing the resulting 'committed dose'.<br/>
'Chronic intake' may, however, be treated as a series of 'acute intakes'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id342skos:definition "A single coherent 'management system' in which all the component parts of <br/>
an organization are integrated to enable the organization’s objectives to be <br/>achieved. <br/>
These component parts include the organizational structure, resources and <br/>organizational 'processes'. <br/>Personnel, equipment and organizational culture, as well as the documented <br/>policies and 'processes', form parts of the 'management system'.<br/>The organizational 'processes' have to address the totality of the <i>requirements<br/></i>on the organization, as established by or in, for example, 'interested parties', <br/>IAEA 'safety standards' and other international codes and standards.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id343skos:definition "An 'event' or a sequence of associated 'events' that, interacting with a <br/>
'facility', affect 'site personnel' or 'items important to safety' in a manner which <br/>could adversely influence 'safety'. <br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id344skos:definition "See 'storage'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id345skos:definition "A portable 'packaging' that:<br/>
(a)<br/>
Has a capacity of not more than 3 m3;<br/>
(b)<br/>
Is designed for mechanical handling;<br/>
(c)<br/>
Is resistant to the stresses produced in handling and 'transport', as <br/>determined by performance tests; <br/>
(d)<br/>
Is designed to conform to the standards in the chapter on Recommendations <br/>on Intermediate Bulk Containers (IBCs) of the United Nations Recommen-<br/>dations on the Transport of Dangerous Goods [26]. (From Ref. [2].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id346skos:definition "See 'waste classes'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id347skos:definition "See 'exposure' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id348skos:definition "See 'transport' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id349skos:definition "Any action intended to reduce or avert 'exposure' or the likelihood of <br/>
'exposure' to 'sources' that are not part of a controlled 'practice' or that are out of <br/>'control' as a consequence of an 'accident'. (From Ref. [1].)<br/>
This definition is somewhat more explicit than (though not necessarily <br/>inconsistent with) that of Ref. [16].<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id35skos:definition "See 'countermeasure'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id350skos:definition "See 'level'.<br/>
<i><b>operational intervention level (OIL).</b></i> See 'level:' 'intervention level'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id351skos:definition "See 'barrier'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id352skos:definition "See 'level'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id353skos:definition "The administration of a compound of stable iodine (usually potassium <br/>
iodide) to prevent or reduce the 'uptake' of 'radioactive' isotopes of iodine by the <br/>thyroid in the 'event' of an 'accident' involving 'radioactive' iodine.<br/>
An 'urgent protective action'.<br/>The term ‘thyroid blocking’ is sometimes used.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id354skos:definition "See 'radiation'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id355skos:definition "A 'structure' or an installation that houses a particle accelerator, X ray <br/>
apparatus or large 'radioactive source' and that can produce high 'radiation' fields. <br/>(From Ref. [1].)<br/>
'Irradiation installations' include installations for external beam <i>radiation<br/></i>therapy, installations for sterilization or preservation of commercial products <br/>and some installations for industrial radiography.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id356skos:definition "See 'plant equipment'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id357skos:definition "1. The 'process' of determining whether a 'practice' is, overall, beneficial, as <br/>
required by the International Commission on Radiological Protection’s <i>System <br/>of Radiological Protection</i>, i.e. whether the benefits to individuals and to <br/>society from introducing or continuing the 'practice' outweigh the harm <br/>(including 'radiation detriment') resulting from the 'practice'.<br/>
2. The 'process' of determining whether a proposed' intervention 'is likely, <br/>
overall, to be beneficial, as required by the International Commission on <br/>Radiological Protection’s 'System of Radiological Protection', i.e. whether the <br/>benefits to individuals and to society (including the reduction in <i>radiation <br/>detriment</i>) from introducing or continuing the 'intervention' outweigh the cost of <br/>the 'intervention' and any harm or damage caused by the 'intervention'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id358skos:definition "The quantity 'K', defined as:<br/>
'E'<br/>
'K '= d tr<br/>
d'm'<br/>
where d'E ' is the sum of the initial kinetic energies of all charged ionizing <br/>
tr<br/>
particles liberated by uncharged ionizing particles in a material of mass d'm'. <br/>(From Ref. [1].)<br/>
Unit: 'gray '(Gy).<br/>Originally an acronym for kinetic energy released in matter, but now accepted <br/>as a word.<br/>
<i><b>air kerma.</b></i> The 'kerma' value for air.<br/>
Under charged particle equilibrium conditions, the 'air kerma' (in 'gray') is <br/>numerically approximately equal to the 'absorbed dose' in air (in 'gray').<br/>
<i><b>reference air kerma rate.</b></i> The 'kerma' rate to air, in air, at a reference <br/>distance of 1 m, corrected for air 'attenuation' and scattering. (From <br/>Ref. [1].)<br/>
This quantity is expressed in µGy/h at 1 m.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id359skos:definition "The 'kerma' per unit 'particle fluence'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id36skos:definition "See 'kerma'.<br/>
See 'kerma'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id360skos:definition "An integrated, systematic approach to identifying, managing and sharing <br/>
an organization’s knowledge and enabling groups of people to create new <br/>knowledge collectively to help in achieving the organization’s objectives.<br/>
In the context of' management systems', 'knowledge management' helps an <br/>organization to gain insight and understanding from its own experience. <br/>Specific 'activities' in 'knowledge management' help the organization to better <br/>acquire, record, store and utilize knowledge'.' <br/>
— The term ‘knowledge’ is often used to refer to bodies of facts and principles <br/>
accumulated by humankind over the course of time. Explicit knowledge is <br/>knowledge that is contained in, for example, documents, drawings, <br/>calculations, 'designs', databases, 'procedures' and manuals. Tacit knowledge is <br/>
knowledge that is held in a person’s mind and has typically not been captured <br/>or transferred in any form (if it were, it would then become explicit <br/>knowledge).<br/>
— Knowledge is distinct from information: data yield information and <br/>
knowledge is gained by acquiring, understanding and interpreting <br/>information. Knowledge and information each consist of true statements, but <br/>knowledge serves a purpose: knowledge confers a capacity for effective <br/>action. <br/>
— Knowledge for an organization is the acquiring, understanding and <br/>
interpreting of information. Knowledge may be applied for such purposes as: <br/>problem solving and learning; forming judgements and opinions; decision <br/>making, forecasting and strategic planning; generating feasible options for <br/>action and taking actions to achieve desired results. Knowledge also protects <br/>intellectual assets from decay, augments intelligence and provides increased <br/>flexibility.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id361skos:definition "See 'freight container'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id362skos:definition "See 'health effects (of radiation)'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id363skos:definition "See 'cause'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id364skos:definition "Any organization, corporation, partnership, firm, association, trust, estate, <br/>
public or private institution, group, political or administrative entity or other person <br/>designated in accordance with national legislation who or which has responsibility <br/>and authority for any action having implications for 'protection and safety'.<br/>
Contrasted in legal texts with natural person, meaning an individual.<br/>See also 'applicant', 'licence' and 'registration'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id365skos:definition "<i><b>action level.</b></i> The level of 'dose rate' or 'activity concentration' above which <br/>'remedial actions' or 'protective actions' should be carried out in <i>chronic <br/>exposure</i> or 'emergency exposure' situations. An 'action level' can also be <br/>expressed in terms of any other measurable quantity as a level above <br/>which 'intervention' should be undertaken.<br/>
<i><b>emergency action level (EAL).</b></i> A specific, predetermined, observable <br/>criterion used to detect, recognize and determine the 'emergency class'.<br/>
An 'emergency action level' could represent an instrument reading, the status of a <br/>piece of equipment or any observable 'event', such as a fire. In this sense, it is not <br/>strictly an 'action level' as defined above, but has essentially the same function.<br/>
<i><b>clearance level.</b></i> A value, established by a 'regulatory body' and expressed <br/>in terms of 'activity concentration' and/or total 'activity', at or below which a <br/>'source' of 'radiation' may be released from 'regulatory control'.<br/>
See also 'clearance' (1).<br/>
<i><b>exemption level.</b></i> A value, established by a 'regulatory body' and expressed <br/>in terms of 'activity concentration', total' activity', 'dose rate' or <i>radiation<br/></i>energy, at or below which a 'source' of 'radiation' may be granted <i>exemption<br/></i>from 'regulatory control' without further consideration.<br/>
A 'regulatory body' may also grant 'exemption' on a case by case basis, following <br/>'notification'. Although the term 'exemption level' does not strictly apply in such <br/>a situation, a criterion for 'exemption' may nevertheless be established by the <br/>'regulatory body', expressed in similar terms or, alternatively, in terms of <br/>'annual dose' on the basis of an appropriate 'dose assessment'. (See para. 5.12 of <br/>Ref. [10] and para. 2.26 of Ref. [27].)<br/>In the BSS [1], the term 'exemption levels' is used, and values are specified in <br/>Table I-I of Schedule I, but neither 'exemption' nor 'exemption level' is defined in <br/>the BSS glossary.<br/>
<i><b>guidance level.</b></i> A level of a specified quantity above which appropriate <br/>actions should be considered. In some circumstances, actions may need to <br/>be considered when the specified quantity is substantially below the <br/>'guidance level'. (From Ref. [1].)<br/>
<i><b>guidance level for medical exposure.</b></i> A value of 'dose', 'dose rate' or <i>activity<br/></i>selected by professional bodies in consultation with the <i>regulatory body<br/></i>to indicate a level above which there should be a review by <i>medical <br/>practitioners</i> in order to determine whether or not the value is excessive, <br/>taking into account the particular circumstances and applying sound <br/>clinical judgement. (From Ref. [1].)<br/>
<i><b>intervention level.</b></i> The level of 'avertable dose' at which a specific <br/>'protective action' is taken in an 'emergency 'or a situation of <i>chronic <br/>exposure</i>.<br/>
<i><b>operational intervention level (OIL).</b></i> A calculated level, measured <br/>by instruments or determined by laboratory analysis, that corresponds <br/>to an 'intervention level' or 'action level'.<br/>
'Operational intervention levels' are typically expressed in terms of <i>dose <br/>rates</i> or of 'activity' of 'radioactive material' released, time integrated air <br/>concentrations, ground or surface concentrations, or <i>activity <br/>concentrations</i> of radionuclides in environmental, food or water samples. <br/>An 'operational intervention level' is a type of 'action level' that is used <br/>immediately and directly (without further 'assessment') to determine the <br/>appropriate 'protective actions' on the basis of an environmental <br/>measurement.<br/>
<i><b>investigation level.</b></i> The value of a quantity such as 'effective dose', <i>intake<br/></i>or 'contamination' per unit area or volume at or above which an <br/>investigation should be conducted. (From Ref. [1].)<br/>
<i><b>level of defence in depth.</b></i> See 'defence in depth'.<br/>
<i><b>recording level.</b></i> A level of 'dose', 'exposure' or 'intake' specified by the <br/>'regulatory body' at or above which values of 'dose', 'exposure' or <i>intake<br/></i>received by 'workers' are to be entered in their individual <i>exposure<br/></i>records. (From Ref. [1].)<br/>
<i><b>reference level.</b></i> An 'action level', 'intervention level', 'investigation level' or <br/>'recording level'. (From Ref. [1].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id366skos:definition "1. A legal document issued by the 'regulatory body' granting 'authorization'<br/>
to perform specified 'activities' related to a 'facility or activity'.<br/>
The holder of a current 'licence' is termed a <i><b>licensee</b></i>. Other derivative terms <br/>should not be needed; a 'licence' is a product of the 'authorization' <i>process<br/></i>(although the term <i><b>licensing process</b></i> is sometimes used), and a 'practice' with a <br/>current 'licence' is an authorized' practice'.<br/>'Authorization' may take other forms, such as 'registration'.<br/>The 'licensee' is the person or organization having overall responsibility for a <br/>'facility' or 'activity' (the <i><b>responsible legal person</b></i>).<br/>
2. [Any 'authorization' granted by the 'regulatory body' to the 'applicant' to <br/>
have the responsibility for the 'siting', 'design', 'construction', 'commissioning', <br/>'operation' or 'decommissioning' of a 'nuclear installation'.] (From Ref. [4].)<br/>
3. [Any 'authorization', permission or certification granted by a 'regulatory'<br/>
'body' to carry out any activity related to management of 'spent fuel' or of <br/>'radioactive waste'.] (From Ref. [5].)<br/>
<b>!</b> The definitions (2) and (3) from the Conventions [4, 5] are somewhat more <br/>
general in scope than the normal IAEA usage in definition (1). In IAEA <br/>usage, a 'licence' is a particular type of 'authorization', normally representing the <br/>primary 'authorization' for the 'operation' of a whole 'facility' or 'activity'. The <br/>conditions attached to the 'licence' may require that further, more specific, <br/>'authorization' or 'approval' be obtained by the 'licensee' before carrying out <br/>particular 'activities'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id367skos:definition "See 'licence' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id368skos:definition "A set of regulatory 'requirements' applicable to a 'nuclear installation'.<br/>
The 'licensing basis', in addition to a set of regulatory 'requirements', may also <br/>include agreements and commitments made between the 'regulatory body' and <br/>the 'licensee' (e.g. in the form of letters exchanged or of statements made in <br/>technical meetings).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id369skos:definition "See 'licence' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id37skos:definition "<i><b>cargo aircraft.</b></i> Any 'aircraft', other than a 'passenger aircraft', which is <br/>carrying goods or property. (From Ref. [2].)<br/>
<i><b>passenger aircraft.</b></i> An 'aircraft' that carries any person other than a crew <br/>member, a 'carrier'’s employee in an official capacity, an authorized <br/>representative of an appropriate national authority, or a person <br/>accompanying a 'consignment'. (From Ref. [2].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id370skos:definition "<i><b>design life.</b></i> The period of time during which a 'facility' or 'component' is <br/>expected to perform according to the technical specifications to which it <br/>was produced.<br/>
<i><b>operating life/lifetime.</b></i> 1. The period during which an <i>authorized facility<br/></i>is used for its intended purpose, until 'decommissioning' or 'closure'.<br/>
The synonyms <i><b>operating period</b></i> and <i><b>operational period</b></i> are also used.<br/>
2. [The period during which a 'spent fuel' or a <i>radioactive waste <br/>management facility</i> is used for its intended purpose. In the case of a <br/>'disposal facility', the period begins when 'spent fuel' or 'radioactive waste' is <br/>first emplaced in the 'facility' and ends upon 'closure' of the 'facility'.] (From <br/>Ref. [5].)<br/>
<i><b>qualified life.</b></i> Period for which a 'structure, system or component' has been <br/>demonstrated, through testing, 'analysis' or experience, to be capable of <br/>functioning within 'acceptance criteria' during specific <i>operating conditions<br/></i>while retaining the ability to perform its 'safety functions' in a <i>design basis <br/>accident</i> or earthquake.<br/>
<i><b>service life.</b></i> The period from initial 'operation' to final withdrawal from <br/>service of a 'structure, system or component'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id371skos:definition "'Life management' (or 'lifetime management') in which due recognition is <br/>
given to the fact that at all stages in the lifetime there may be effects that need <br/>to be taken into consideration.<br/>
An example is the approach to products, 'processes' and services in which it is <br/>recognized that at all stages in the lifetime of a product (extraction and <br/>processing of raw materials, manufacturing, 'transport' and distribution, use <br/>and reuse, and recycling and 'waste' management) there are environmental and <br/>economic impacts.<br/>The term ‘life cycle’ (as opposed to lifetime) implies that the life is genuinely <br/>cyclical (as in the case of recycling or 'reprocessing').<br/>See 'cradle to grave' 'approach'.<br/>See 'ageing management'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id372skos:definition "See 'ageing management'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id373skos:definition "See 'dose concepts'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id374skos:definition "See 'risk' (3).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id375skos:definition "The value of a quantity used in certain specified 'activities' or <br/>
circumstances that must not be exceeded. (From Ref. [1].)<br/>
<b>!</b> The term 'limit' should only be used for a criterion that must not be exceeded, e.g. <br/>
where exceeding the 'limit' would cause some form of legal sanction to be <br/>invoked. Criteria used for other purposes — e.g. to indicate a need for closer <br/>investigation or a review of 'procedures', or as a threshold for reporting to a <br/>'regulatory body' — should be described using other terms, such as 'reference level'.<br/>
<i><b>acceptable limit.</b></i> A 'limit' acceptable to the 'regulatory body'.<br/>
The term 'acceptable limit' is usually used to refer to a 'limit' on the predicted <br/>radiological consequences of an 'accident' (or on 'potential exposures' if they <br/>occur) that is acceptable to the relevant 'regulatory body' when the probability <br/>of occurrence of the 'accident' or 'potential exposures' has been taken into <br/>
account (i.e. on the basis that it is unlikely to occur). The term <i>authorized limit<br/></i>should be used to refer to 'limits' on 'doses' or 'risks', or on releases of <br/>radionuclides, which are acceptable to the 'regulatory body' on the assumption <br/>that they are likely to occur.<br/>
<i><b>annual limit on exposure (ALE).</b></i> The 'potential alpha energy exposure' in <br/>a year that would result in inhalation of the 'annual limit on intake (ALI)'.<br/>
Used for 'exposure' to 'radon progeny' and 'thoron progeny'.<br/>In units of J·h/m3.<br/>
<i><b>annual limit on intake (ALI).</b> </i>The 'intake' by inhalation or ingestion or <br/>through the skin of a given radionuclide in a year by 'Reference Man' which <br/>would result in a 'committed dose' equal to the relevant 'dose limit'. (From <br/>Ref. [1].)<br/>
The 'annual limit on intake' is expressed in units of 'activity'.<br/>See Ref. [28].<br/>
<i><b>authorized limit.</b></i> A 'limit' on a measurable quantity, established or <br/>formally accepted by a 'regulatory body'.<br/>
<b>!</b> Wherever possible, 'authorized limit' should be used in preference to <br/>
'prescribed limit'.<br/>Equivalent in meaning to 'prescribed limit', 'authorized limit' has been more <br/>commonly used in 'radiation' 'safety' and 'waste' 'safety', particularly in the context <br/>of 'limits' on 'discharges'.<br/>
<i><b>derived limit.</b></i> A 'limit' on a measurable quantity set, on the basis of a <br/>'model', such that compliance with the 'derived limit' may be assumed to <br/>ensure compliance with a 'primary limit'.<br/>
<i><b>dose limit.</b></i> The value of the 'effective dose' or the 'equivalent dose' to <br/>individuals from controlled 'practices' that shall not be exceeded. (From <br/>Ref. [1].)<br/>
<i><b>operational limits and conditions.</b></i> A set of rules setting forth parameter <br/>'limits', the functional capability and the performance levels of equipment <br/>and personnel approved by the 'regulatory body' for safe 'operation' of an <br/>'authorized facility'.<br/>
<b>['prescribed limit'</b><b>]'.'</b> A 'limit' established or accepted by the 'regulatory body'.<br/>
The term 'authorized limit' is preferred.<br/>
<i><b>primary limit.</b></i> A 'limit' on the 'dose' or 'risk' to an individual.<br/>
<i><b>safety limits.</b></i> 'Limits' on operational parameters within which an <br/>'authorized facility' has been shown to be safe.<br/>
'Safety limits' are 'operational limits and conditions' beyond those for <i>normal <br/>operation</i>.<br/>
<b>['secondary limit'</b><b>]'.'</b> A 'limit' on a measurable quantity that corresponds to a <br/>'primary limit'.<br/>
<b>!</b> Such <br/>
a <br/>
'limit' meets the definition of 'derived limit', and 'derived limit' should be <br/>
used.<br/>E.g. the 'annual limit on intake', a 'secondary limit', corresponds to the <i>primary <br/>limit</i> on 'annual effective dose' for a 'worker'.<br/>
<b>linear energy transfer (LET), 'L'</b>Δ<br/>
Defined generally as:<br/>
d'E 'ˆ<br/>
'L'D = ÊËÁ d ¯˜ D<br/>
where d'E' is the energy lost in traversing distance d and Δ is an upper bound on <br/>the energy transferred in any single collision.<br/>
A measure of how, as a function of distance, energy is transferred from <br/>'radiation' to the exposed matter. A high value of <i>linear energy transfer<br/></i>indicates that energy is deposited within a small distance.<br/>'L'∞ (i.e. with Δ = ∞) is termed the <i><b>unrestricted linear energy transfer</b></i> in <br/>defining the 'quality factor'.<br/>'L'Δ is also known as the <i><b>restricted linear collision stopping power</b></i>.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id376skos:definition "The hypothesis that the 'risk' of 'stochastic effects' is directly proportional to <br/>
the 'dose' for all levels of 'dose' and 'dose rate' (below those at which <i>deterministic <br/>effects</i> occur).<br/>
I.e. that any non-zero 'dose' implies a non-zero 'risk' of 'stochastic effects'.<br/>This is the working hypothesis on which the IAEA’s 'safety standards' (and the <br/>International Commission on Radiological Protection’s recommendations) <br/>are based. It is not proven — indeed it is probably not provable — for low <br/>'doses' and 'dose rates', but it is considered the most radiobiologically defensible <br/>assumption on which to base 'safety standards'. Other hypotheses conjecture <br/>that the 'risk' of 'stochastic effects' at low 'doses' and/or 'dose rates' is:<br/>(a) Greater than that implied by the 'linear–no threshold hypothesis'<br/>
(superlinear hypotheses);<br/>
(b) Less than that implied by the 'linear–no threshold hypothesis' (sublinear <br/>
hypotheses);<br/>
(c) Zero below some threshold value of 'dose' or 'dose rate' (threshold <br/>
hypotheses); or<br/>
(d) Negative below some threshold value of 'dose' or 'dose rate', i.e. that low <br/>
'doses' and 'dose rates' protect individuals against 'stochastic effects' and/or <br/>other types of harm (hormesis hypotheses).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id377skos:definition "See 'probabilistic safety assessment (PSA)'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id378skos:definition "The generation of a required binary output signal from a number of <br/>
binary input signals according to predetermined rules, or the equipment used <br/>for generating this signal.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id379skos:definition "See 'waste classes'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id38skos:definition "See 'optimization of protection (and safety)'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id380skos:definition "See 'protective action' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id381skos:definition "See 'waste classes'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id382skos:definition "Either solid 'radioactive material', or solid 'radioactive material' in a sealed <br/>
capsule, that has limited dispersibility and is not in powder form. (From <br/>Ref. [2].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id383skos:definition "See 'uranium'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id384skos:definition "See 'radiation'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id385skos:definition "See 'waste classes'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id386skos:definition "<b>!</b> This usage is specific to the Transport Regulations, and should otherwise be <br/>
avoided.<br/>
'Radioactive material' which by its nature has a limited 'specific activity', or <br/>
'radioactive material' for which 'limits' of estimated average 'specific activity' apply. <br/>External shielding materials surrounding the 'low specific activity material' shall <br/>not be considered in determining the estimated average 'specific activity'.<br/>
'Low specific activity material' shall be [classified] in one of three groups:<br/>
(a)<br/>
<i><b>LSA-I</b></i><br/>
1. Uranium and thorium ores and concentrates of such ores, and other <br/>
ores containing 'naturally occurring radionuclides' which are intended <br/>to be processed for the use of these radionuclides;<br/>
2. 'Natural uranium', 'depleted uranium', natural thorium or their <br/>
compounds or mixtures, provided that they are unirradiated and in <br/>solid or liquid form;<br/>
3. 'Radioactive material' for which the 'A ' value is unlimited, excluding <br/>
'2'<br/>
'fissile material' in quantities not excepted under para. 672 [of Ref. [2]]; <br/>or<br/>
4. Other 'radioactive material' in which the 'activity' is distributed <br/>
throughout and the estimated average 'specific activity' does not <br/>exceed 30 times the values for 'activity concentration' specified in paras <br/>401–406 [of Ref. [2]], excluding 'fissile material' in quantities not <br/>excepted under para. 672 [of Ref. [2]].<br/>
(b)<br/>
<i><b>LSA-II</b></i><br/>
1. Water with tritium concentration up to 0.8 TBq/L; or<br/>
2. Other material in which the 'activity' is distributed throughout and the <br/>
estimated average 'specific activity' does not exceed 10–4 'A '/g for solids <br/>
'2'<br/>
and gases, and 10–5 'A '/g for liquids.<br/>
'2'<br/>
(c)<br/>
<i><b>LSA-III</b></i><br/>
Solids (e.g. consolidated 'waste', activated material), excluding powders, in <br/>
which:<br/>
1. The 'radioactive material' is distributed throughout a solid or a <br/>
collection of solid objects, or is essentially uniformly distributed in a <br/>solid compact binding agent (such as concrete, bitumen, ceramic, <br/>etc.);<br/>
2. The 'radioactive material' is relatively insoluble, or is intrinsically <br/>
contained in a relatively insoluble matrix, so that, even under loss of <br/>'packaging', the loss of 'radioactive material' per 'package' by leaching <br/>when placed in water for seven days would not exceed 0.1 'A '; and<br/>
'2'<br/>
3. The estimated average 'specific activity' of the solid, excluding any <br/>
shielding material, does not exceed 2 × 10–3 'A '/g. (From Ref. [2].)<br/>
'2'<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id387skos:definition "'Natural uranium'; 'depleted uranium'; natural thorium; uranium-235 or <br/>
uranium-238; thorium-232; thorium-228 and thorium-230 when contained in <br/>ores or physical and chemical concentrates; or alpha emitters with a 'half-life' of <br/>less than 10 days. (From Ref. [2].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id388skos:definition "See 'minimum detectable activity (MDA)'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id389skos:definition "A classification used to distinguish between the different rates at which <br/>
inhaled radionuclides are transferred from the respiratory tract to the blood.<br/>
Reference [29] classifies materials into three 'lung absorption types':<br/>(a) Type F (fast) are materials that are readily absorbed into the blood;<br/>(b) Type M (moderate) are materials that have intermediate rates of <br/>
absorption into the blood;<br/>
(c) Type S (slow) are materials that are relatively insoluble and are only <br/>
slowly absorbed into the blood.<br/>
The 'lung absorption types' supersede the <i><b>inhalation classes</b></i> D (days), M <br/>(months) and Y (years) previously recommended in Ref. [15] (often referred <br/>
to informally as ‘lung classes’). There is an approximate correspondence <br/>between 'lung absorption type' F and 'inhalation class' D, between <i>lung <br/>absorption type</i> M and 'inhalation class' M and between 'lung absorption type' S <br/>and 'inhalation class' Y.<br/>See also 'gut transfer factor', a similar concept for ingested radionuclides in the <br/>gastrointestinal tract.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id39skos:definition "See 'emergency class'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id390skos:definition "See 'safety function'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id391skos:definition "The organized activity, both administrative and technical, of keeping<br/>
'structures, systems and components' in good operating condition, including both <br/>preventive and corrective (or 'repair') aspects.<br/>
<i><b>corrective maintenance.</b></i> Actions that restore, by 'repair', overhaul or <br/>replacement, the capability of a failed 'structure, system or component' to <br/>function within 'acceptance criteria'.<br/>
Contrasted with 'preventive maintenance'.<br/>
<i><b>periodic maintenance.</b></i> Form of 'preventive maintenance' consisting of <br/>servicing, parts replacement, surveillance or testing at predetermined <br/>intervals of calendar time, operating time or number of cycles.<br/>
Also termed <i><b>time based maintenance</b></i>.<br/>
<i><b>planned maintenance.</b></i> Form of 'preventive maintenance' consisting of <br/>refurbishment or replacement that is scheduled and performed prior to <br/>unacceptable degradation of a' structure, system or component'.<br/>
<i><b>predictive maintenance.</b></i> Form of 'preventive maintenance' performed <br/>continuously or at intervals governed by observed condition to monitor, <br/>diagnose or trend a 'structure, system or component'’s 'condition indicators'; <br/>results indicate present and future functional ability or the nature of and <br/>schedule for 'planned maintenance'.<br/>
Also termed <i><b>condition based maintenance</b></i>.<br/>
<i><b>preventive maintenance.</b></i> Actions that detect, preclude or mitigate <br/>degradation of a functional 'structure, system or component' to sustain or <br/>extend its useful life by controlling degradation and 'failures' to an <br/>acceptable level.<br/>
'Preventive maintenance' may be 'periodic maintenance', 'planned maintenance' or <br/>'predictive maintenance'.<br/>Contrasted with 'corrective maintenance'.<br/>
<i><b>reliability centred maintenance (RCM).</b></i> A 'process' for specifying <br/>applicable 'preventive maintenance' requirements for <i>safety related systems<br/></i>and equipment in order to prevent potential 'failures' or to control the <br/>'failure modes' optimally. 'RCM' utilizes a decision 'logic' tree to identify the <br/>'maintenance' requirements according to the 'safety' consequences and <br/>operational consequences of each 'failure' and the degradation mechanism <br/>responsible for the 'failures'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id392skos:definition "See 'bypass' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id393skos:definition "See 'INES'.<br/>
See 'INES'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id394skos:definition "The intention to do evil. <br/>
In law, wrongful intention, especially as increasing the guilt of certain <br/>offences. See also 'malevolent'.<br/>
<i><b>malice aforethought, malicious intent.</b></i> In law, the intention to commit a <br/>crime.<br/>
<i><b>malicious.</b></i> Characterized by 'malice'; intending or intended to do harm.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id395skos:definition "An instance of wishing evil to others. <br/>
See also 'malice'. Often used interchangeably with 'malice'. However, <i>malice<br/></i>relates to acts or the intention to commit acts. Since the term 'malice' has an <br/>established usage under the law, it should be preferred if this is what is meant.<br/>
<i><b>malevolent.</b></i> Characterized by 'malevolence'; wishing evil to others.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id396skos:definition "[The administrative and operational 'activities' that are involved in the <br/>
manufacture, supply, receipt, possession, 'storage', use, transfer, import, export, <br/>
'transport', 'maintenance', recycling or 'disposal' of 'radioactive sources'.] (From <br/>Ref. [11].)<br/>
This usage is specific to the Code of Conduct on the Safety and Security of <br/>Radioactive Sources [11].<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id397skos:definition "See 'assessment' (2).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id398skos:definition "A set of interrelated or interacting elements (system) for establishing <br/>
policies and objectives and enabling the objectives to be achieved in an <br/>efficient and effective manner.<br/>
The component parts of the 'management system' include the organizational <br/>structure, resources and organizational 'processes'. Management is defined (in <br/>ISO 9000) as coordinated 'activities' to direct and 'control' an organization.<br/>The 'management system' integrates all elements of an organization into one <br/>coherent system to enable all of the organization’s objectives to be achieved. <br/>These elements include the organizational structure, resources and 'processes'. <br/>Personnel, equipment and organizational culture as well as the documented <br/>policies and 'processes' are parts of the 'management system'. The organization’s <br/>'processes' have to address the totality of the 'requirements' on the organization <br/>as established in, for example, IAEA 'safety standards' and other international <br/>codes and standards.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id399skos:definition "A regular and systematic evaluation by 'senior management' of an <br/>
organization of the suitability, adequacy, effectiveness and efficiency of its <br/>'management system' in executing the policies and achieving the goals and <br/>objectives of the organization.<br/>
<i><b>Senior management</b></i> means the person who, or group of people which, directs, <br/>controls and assesses an organization at the highest level.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id4skos:definition "See 'dose quantities'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id40skos:definition "See 'dose equivalent quantities'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id400skos:definition "See 'ageing'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id401skos:definition "See 'model'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id402skos:definition "The maximum pressure above atmospheric pressure at mean sea level <br/>
that would develop in the 'containment system' in a period of one year under the <br/>conditions of temperature and solar 'radiation' corresponding to environmental <br/>conditions in the absence of venting, external cooling by an ancillary 'system' or <br/>operational 'controls' during 'transport'. (From Ref. [2].)<br/>
<b>!</b> This usage is specific to the Transport Regulations.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id403skos:definition "See 'exposure, types of'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id404skos:definition "An individual who: (a) has been accredited through appropriate national <br/>
'procedures' as a 'health professional'; (b) fulfils the national 'requirements' on <br/>training and experience for prescribing 'procedures' involving 'medical exposure'; <br/>and (c) is a 'registrant' or a 'licensee' or a 'worker' who has been designated by a <br/>registered or licensed 'employer' for the purpose of prescribing <i>procedures<br/></i>involving 'medical exposure'. (From Ref. [1].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id405skos:definition "See 'waste classes'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id406skos:definition "In a general sense, any individual in the population except, for 'protection '<br/>
'and safety' purposes, when subject to 'occupational' or 'medical exposure'. For the <br/>purpose of verifying compliance with the 'annual dose limit' for 'public exposure', <br/>the representative individual in the relevant 'critical group'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id407skos:definition "The movement of radionuclides in the environment as a result of natural <br/>
'processes'.<br/>
Most commonly, movement of radionuclides in association with groundwater <br/>flow.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id408skos:definition "See ['mine or mill processing radioactive ores'].<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id409skos:definition "See ['mining and milling'].<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id41skos:definition "Often used interchangeably with 'assessment', especially in more specific terms <br/>such as ‘'safety' 'analysis'’. In general, however, 'analysis' suggests the 'process' and <br/>result of a study aimed at understanding the subject of the 'analysis', while <br/>'assessment' may also include determinations or judgements of acceptability. <br/>'Analysis' is also often associated with the use of a specific technique. Hence, <br/>one or more forms of 'analysis' may be used in 'assessment'.<br/>
<i><b>cost–benefit analysis.</b></i> A systematic economic evaluation of the positive <br/>effects (benefits) and negative effects (disbenefits, including monetary <br/>costs) of undertaking an action.<br/>
A decision aiding technique commonly used in the 'optimization' <i>of protection <br/>and safety</i>. This and other techniques are discussed in Ref. [8].<br/>
<i><b>event tree analysis.</b></i> An inductive technique that starts by hypothesizing <br/>the occurrence of basic 'initiating events' and proceeds through their logical <br/>propagation to 'system failure' 'events'.<br/>
The 'event' tree is the diagrammatic illustration of alternative outcomes of <br/>specified 'initiating events'.<br/>'Fault tree analysis' considers similar chains of 'events', but starts at the other end <br/>(i.e. with the ‘results’ rather than the ‘causes’). The completed 'event' trees and <br/>fault trees for a given set of 'events' would be similar to one another.<br/>
<i><b>fault tree analysis.</b></i> A deductive technique that starts by hypothesizing <br/>and defining 'failure' 'events' and systematically deduces the 'events' or <br/>combinations of 'events 'that caused the 'failure' 'events' to occur.<br/>
The fault tree is the diagrammatic illustration of the 'events'.<br/>'Event tree analysis' considers similar chains of 'events', but starts at the other <br/>end (i.e. with the ‘causes’ rather than the ‘results’). The completed 'event' trees <br/>and fault trees for a given set of 'events' would be similar to one another.<br/>
<i><b>safety analysis.</b></i> Evaluation of the potential hazards associated with the <br/>conduct of an 'activity'.<br/>
'Safety analysis' is often used interchangeably with 'safety assessment'. However, <br/>when the distinction is important, 'safety analysis' should be used for the study <br/>of 'safety', and 'safety assessment' for the evaluation of 'safety' — for example, <br/>evaluation of the magnitude of hazards, evaluation of the performance of <br/>'safety measures' and judgement of their adequacy, or quantification of the <br/>overall radiological impact or 'safety' of a 'facility 'or 'activity'.' '<br/>
<i><b>sensitivity analysis.</b></i> A quantitative examination of how the behaviour of <br/>a 'system' varies with change, usually in the values of the governing <br/>parameters.<br/>
A common approach is parameter variation, in which the variation of results <br/>is investigated for changes in the value of one or more input parameters <br/>within a reasonable range around selected reference or mean values, and <br/>perturbation 'analysis', in which the variations of results with respect to <br/>changes in the values of all the input parameters are obtained by applying <br/>differential or integral 'analysis'.<br/>
<i><b>uncertainty analysis.</b></i> An 'analysis' to estimate the uncertainties and error <br/>bounds of the quantities involved in, and the results from, the solution of <br/>a problem.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id410skos:definition "[Installation for mining, milling or processing ores containing 'uranium '<br/>
'series' or 'thorium series 'radionuclides. A mine processing 'radioactive' ores is any <br/>mine that yields ores containing 'uranium series' or 'thorium series 'radionuclides, <br/>either in sufficient quantities or concentrations to warrant exploitation or, <br/>when present in conjunction with other substances being mined, in quantities <br/>or concentrations that require 'radiation protection' measures to be taken as <br/>determined by the 'Regulatory Authority'. A mill processing 'radioactive' ores' 'is <br/>any 'facility' for processing 'radioactive 'ores from a mine processing <i>radioactive<br/></i>ores' 'as here defined to produce a physical or chemical concentrate.] (From <br/>Ref. [1].)<br/>
This definition from the BSS included those mining and processing <i>operations<br/></i>aimed at extracting 'uranium series' or 'thorium series' radionuclides and those <br/>aimed at the extraction of other substances from ore where this represents a <br/>significant radiological hazard.<br/>Strictly speaking, a mill in the context of the processing of minerals is a <i>facility<br/></i>for the processing of ore to reduce its particle size, especially by crushing or <br/>grinding. However, in the context of the BSS definition, the term 'mill' is used <br/>in a broader sense to denote a 'facility' in which additional (e.g. <br/>hydrometallurgical) processing may also be carried out. Owing to the <br/>possibility of confusion, the use of the word 'mill' in this broader sense, in this <br/>expression or elsewhere, is discouraged.<br/>This definition has been included for information only. Words are used with <br/>their normal dictionary definitions except for the term 'radioactive'. See <br/>'radioactive' (2).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id411skos:definition "The 'process' of reducing the amount and 'activity' of 'radioactive waste' to a <br/>
level as low as reasonably achievable, at all stages from the 'design' of a <i>facility <br/>or activity</i> to 'decommissioning', by reducing 'waste' generation and by means <br/>such as recycling and reuse, and 'treatment', with due consideration for <br/>secondary as well as primary 'waste'.<br/>
Should not be confused with' volume reduction'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id412skos:definition "The 'radioactivity' which, if present in a sample, produces a counting rate <br/>
that will be detected (i.e. considered to be above 'background') with a certain <br/>level of confidence.<br/>
The ‘certain level of confidence’ is normally set at 95%, i.e. a sample <br/>containing exactly the 'minimum detectable activity' will, as a result of random <br/>fluctuations, be taken to be free of 'radioactivity' 5% of the time.<br/>The 'minimum detectable activity' is sometimes referred to as the <i><b>detection <br/>limit</b></i> or <i><b>lower limit of detection</b></i>. The counting rate from a sample containing <br/>the 'minimum detectable activity' is termed the <i><b>determination level</b></i>.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id413skos:definition "The 'radioactivity' which, if present in a sample, produces a counting rate <br/>
that can be reliably distinguished from 'background' with a certain level of <br/>confidence.<br/>
A sample containing exactly the 'minimum significant activity' will, as a result <br/>of random fluctuations, be taken to be free of 'radioactivity' 50% of the time, <br/>whereas a true 'background' sample will be taken to be free of <i>radioactivity<br/></i>95% of the time.<br/>The 'minimum significant activity' is sometimes referred to as the <i><b>decision <br/>limit</b></i>. The counting rate from a sample containing the <i>minimum significant <br/>activity</i> is termed the <i><b>critical level</b></i>.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id414skos:definition "[Mining in a mine that yields 'radioactive ore' containing 'uranium series' or <br/>
'thorium series' radionuclides either in amounts or concentrations sufficient to <br/>warrant exploitation or, when present in conjunction with other substances <br/>being mined, in amounts or concentrations that require <i>radiation protection<br/></i>measures to be taken; and processing of 'radioactive ores' from such mines to <br/>produce a chemical concentrate.]<br/>
This definition was restricted to those mining and processing operations <br/>aimed at extracting 'uranium series' or 'thorium series' radionuclides and those <br/>aimed at extracting other substances from ore that represent a significant <br/>radiological hazard. This definition has been included for information only. <br/>The terms 'mining' and 'milling' should be used with their normal dictionary <br/>definitions, qualified where necessary (e.g. by use of the term 'radioactive').<br/>Strictly speaking, milling in the context of the processing of minerals is the <br/>processing of ore to reduce its particle size, especially by crushing or grinding. <br/>However, in the context of this definition, the term 'milling' is used in a <br/>broader sense to include additional (e.g. hydrometallurgical) processing. <br/>
Owing to the possibility of confusion, the use of the word 'milling' in this <br/>broader sense, in this expression or elsewhere, is discouraged.<br/>
<b>!</b> See <br/>
'mine or mill processing radioactive ores'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id415skos:definition "See 'waste'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id416skos:definition "See 'protective action '(1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id417skos:definition "See 'waste'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id418skos:definition "An analytical representation or quantification of a real system and the <br/>
ways in which phenomena occur within that system, used to predict or assess <br/>the behaviour of the real system under specified (often hypothetical) <br/>conditions.<br/>
<i><b>computational model.</b></i> A calculational tool that implements a <br/>'mathematical model'.<br/>
<i><b>conceptual model.</b></i> A set of qualitative assumptions used to describe a <br/>system (or part thereof).<br/>
These assumptions would normally cover, as a minimum, the geometry and <br/>dimensionality of the system, initial and boundary conditions, time <br/>dependence, and the nature of the relevant physical, chemical and biological <br/>'processes' and phenomena.<br/>
<i><b>mathematical model.</b></i> A set of mathematical equations designed to <br/>represent a 'conceptual model'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id419skos:definition "See 'calibration'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id42skos:definition "See 'dose concepts'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id420skos:definition "See 'validation' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id421skos:definition "See 'verification' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id422skos:definition "1. The measurement of 'dose' or 'contamination' for reasons related to the <br/>
'assessment' or 'control' of 'exposure' to 'radiation' or 'radioactive substances', and the <br/>interpretation of the results. (From Ref. [1].)<br/>
‘Measurement’ is used somewhat loosely here. The ‘measurement’ of <i>dose<br/></i>often means the measurement of a 'dose equivalent quantity' as a proxy (i.e. <br/>substitute) for a 'dose quantity' that cannot be measured directly. Also, <br/>sampling may be involved as a preliminary step to measurement.<br/>'Monitoring' may be subdivided in two different ways: according to where the <br/>measurements are made, into 'individual monitoring', 'workplace monitoring', <br/>'source monitoring' and 'environmental monitoring'; and, according to the <br/>purpose of the 'monitoring', into 'routine monitoring', <i>task related monitoring<br/></i>and 'special monitoring'.<br/>
<i><b>area monitoring.</b></i> A form of 'workplace monitoring' in which an area is <br/>monitored by taking measurements at different points in that area.<br/>
As opposed to measurements by a static monitor.<br/>
<i><b>environmental monitoring.</b></i> The measurement of 'external dose' rates due <br/>to 'sources' in the environment or of radionuclide concentrations in <br/>environmental media.<br/>
Contrasted with 'source monitoring'.<br/>
<i><b>individual monitoring.</b></i> 'Monitoring' using measurements by equipment <br/>worn by individual 'workers', or measurements of quantities of <i>radioactive <br/>material</i> in or on their bodies.<br/>
Also called 'personal monitoring'. Usually contrasted with <i>workplace <br/>monitoring</i>.<br/>
<b>['personal monitoring'</b><b>]'.'</b> Synonymous with 'individual monitoring'.<br/>
This usage may be confusing and is discouraged in favour of <i>individual <br/>monitoring</i>.<br/>
<b>['personnel monitoring'</b><b>]'.'</b> A combination of 'individual monitoring' and <br/>'workplace monitoring'.<br/>
This usage may be confusing and is discouraged in favour of <i>individual <br/>monitoring </i>and/or' workplace monitoring', as appropriate.<br/>
<i><b>routine monitoring.</b></i> 'Monitoring' associated with continuing <i>operations<br/></i>and intended: (1) to demonstrate that working conditions, including the <br/>levels of 'individual dose', remain satisfactory; and (2) to meet regulatory <br/>'requirements'.<br/>
'Routine monitoring' can be 'individual monitoring' or 'workplace monitoring'.<br/>Contrasting terms: 'task related monitoring' and 'special monitoring'.<br/>
<i><b>source monitoring.</b></i> The measurement of 'activity' in <i>radioactive material<br/></i>being released to the environment or of 'external dose' rates due to <i>sources<br/></i>within a 'facility or activity'.<br/>
Contrasted with 'environmental monitoring'.<br/>
<i><b>special monitoring.</b></i> 'Monitoring' designed to investigate a specific <br/>situation in the workplace for which insufficient information is available <br/>to demonstrate adequate 'control', by providing detailed information to <br/>elucidate any problems and to define future 'procedures'.<br/>
'Special monitoring' would normally be undertaken at the 'commissioning' stage <br/>of new 'facilities', following major modifications either to 'facilities' or to <br/>'procedures', or when 'operations' are being carried out under abnormal <br/>circumstances, such as following an 'accident'.<br/>'Special monitoring' can be 'individual monitoring' or 'workplace monitoring'.<br/>Contrasting terms: 'routine monitoring' and 'task related monitoring'.<br/>
<i><b>task related monitoring.</b></i> 'Monitoring' in relation to a specific 'operation', to <br/>provide data to support immediate decisions on the management of the <br/>'operation'.<br/>
'Task related monitoring' can be 'individual monitoring' or <i>workplace <br/>monitoring</i>.<br/>Contrasting terms: 'routine monitoring' and 'special monitoring'.<br/>
<i><b>workplace monitoring.</b></i> 'Monitoring' using measurements made in the <br/>working environment.<br/>
Usually contrasted with 'individual monitoring'.<br/>
2. Continuous or periodic measurement of radiological or other <br/>
parameters or determination of the status of a 'structure,' 'system or component'. <br/>Sampling may be involved as a preliminary step to measurement.<br/>
Although the concept is not fundamentally different from definition (1), this <br/>definition is more suited to the types of 'monitoring' concerned primarily with <br/>'safety' (i.e. keeping 'sources' under 'control') rather than with 'protection' (i.e. <br/>controlling 'exposure'). This definition is particularly relevant to <i>monitoring<br/></i>the status of a 'nuclear installation' by tracking plant variables, or <i>monitoring<br/></i>the long term performance of a 'waste repository' by tracking variables such as <br/>water fluxes. These examples differ from definition (1) in that the routine <br/>measurements are themselves of no particular interest; the 'monitoring' is only <br/>intended to detect unexpected 'deviations' if they occur.<br/>
<i><b>condition monitoring.</b></i> Continuous or periodic tests, 'inspections', <br/>measurement or trending of the performance or physical characteristics <br/>of 'structures, systems and components' to indicate current or future <br/>performance and the potential for 'failure'.<br/>
'Condition monitoring' is usually conducted on a non-intrusive basis.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id423skos:definition "See 'approval'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id424skos:definition "See 'barrier'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id425skos:definition "Transmission and reception of two or more signals or messages over a <br/>
single data 'channel', e.g. by the use of time division, frequency division or pulse <br/>code techniques.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id426skos:definition "See 'risk projection model'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id427skos:definition "A situation in nature that is used as a 'model' for 'processes' affecting human-<br/>made systems, allowing conclusions to be drawn that are relevant for making <br/>judgements about the 'safety' of an existing or planned 'nuclear facility'. In <br/>particular, mineral deposits containing radionuclides whose 'migration' history <br/>over very long time periods can be analysed and the results used in modelling <br/>the potential behaviour of these or similar radionuclides in the 'geosphere' over <br/>a long period of time.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id428skos:definition "See 'background'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id429skos:definition "See 'source' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id43skos:definition "See 'limit'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id430skos:definition "See 'uranium'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id431skos:definition "'Radioactive material' containing no significant amounts of radionuclides <br/>
other than 'naturally occurring radionuclides'.<br/>
The exact definition of ‘significant amounts’ would be a regulatory decision.<br/>Material in which the 'activity concentrations' of the <i>naturally occurring <br/>radionuclides</i> have been changed by a 'process' is included in <i>naturally <br/>occurring radioactive material</i>.<br/>'Naturally occurring radioactive material' or 'NORM' should be used in the <br/>singular unless reference is explicitly being made to various materials.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id432skos:definition "See 'radionuclides of natural origin'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id433skos:definition "The excavated area of a 'repository' near or in contact with the 'waste '<br/>
'packages', including filling or sealing materials, and those parts of the host <br/>
medium/rock whose characteristics have been or could be altered by the <br/>'repository' or its contents.<br/>
See also 'far field'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id434skos:definition "A potential significant 'event' that could have occurred as the consequence <br/>
of a sequence of actual occurrences but did not occur owing to the plant <br/>conditions prevailing at the time.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id435skos:definition "See 'disposal' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id436skos:definition "See 'repository'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id437skos:definition "See 'nuclear fuel'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id438skos:definition "See 'contamination' (2).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id439skos:definition "See 'ageing'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id44skos:definition "See 'limit'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id440skos:definition "See 'health effects (of radiation):' 'deterministic effect'.<br/>
See 'health effects (of radiation):' 'deterministic effect'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id441skos:definition "See 'naturally occurring radioactive material'.<br/>
See 'naturally occurring radioactive material'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id442skos:definition "Material that remains from a 'process' and comprises or is contaminated by <br/>
'naturally occurring radioactive material (NORM)'.<br/>
A 'NORM residue' may or may not be 'waste'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id443skos:definition "See 'waste'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id444skos:definition "See 'exposure situations'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id445skos:definition "See 'plant states'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id446skos:definition "1. A document submitted to the 'regulatory body' by a 'legal person' to <br/>
notify an intention to carry out a 'practice' or other use of a 'source'.<br/>
This includes the 'notification' of appropriate 'competent authorities' by a <br/>'consignor' that a 'shipment' will pass through or into their countries, as <i>required<br/></i>under paras 558–561 of the 2005 edition of the Transport Regulations [2].<br/>
2. A report submitted promptly to a national or international authority <br/>
providing details of an 'emergency' or a possible 'emergency'; for example, as <br/>'required' by the Convention on Early Notification of a Nuclear Accident.<br/>
3. A set of actions taken upon detection of 'emergency' conditions with the <br/>
purpose of alerting all organizations with responsibility for <i>emergency response<br/></i>in the event of such conditions.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id447skos:definition "A designated organization with which 'arrangements' have been made to <br/>
receive 'notification' (3) and to initiate promptly the predetermined actions to <br/>activate a part of the 'emergency response'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id448skos:definition "The State that is responsible for notifying (see 'notification' (2)) potentially <br/>
affected States and the IAEA of an 'event' or situation of actual, potential or <br/>perceived radiological significance for other States. This includes:<br/>
(a)<br/>
The State Party that has jurisdiction or 'control' over the 'facility' or <i>activity<br/></i>(including space objects) in accordance with Article 1 of the Convention <br/>on Early Notification of a Nuclear Accident [6]; or<br/>
(b)<br/>
The State that initially detects, or discovers evidence of, a <i>transnational <br/>emergency</i>, for example by: detecting significant increases in atmospheric <br/>'radiation levels' of unknown origin; detecting 'contamination' in <br/>transboundary 'shipments'; discovering a 'dangerous source' that may have <br/>originated in another State; or diagnosing medical symptoms that may <br/>have resulted from 'exposure' outside the State.<br/>
<b>nuclear </b>'(adjective)'<br/>
Strictly: relating to a nucleus; relating to or using energy released in nuclear <br/>fission or fusion.<br/>
<b>!</b> The adjective ‘nuclear’ is used in many phrases to modify a noun that it <br/>
cannot logically modify. It must be borne in mind that the meaning of such <br/>phrases may be unclear. These phrases may therefore be open to <br/>misunderstanding, misrepresentation or mistranslation, and their usage may <br/>need to be explained. Such phrases include: nuclear accident; nuclear <br/>community; nuclear emergency; nuclear facility; nuclear fuel; nuclear <br/>incident; nuclear installation; nuclear material; nuclear medicine; [a] nuclear <br/>power; nuclear sabotage; nuclear safety; nuclear security; nuclear terrorism; <br/>nuclear trafficking; nuclear watchdog; and nuclear weapon. For example, <br/>strictly speaking, ‘nuclear material’ primarily means the material of the <br/>atomic nucleus.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id449skos:definition "See 'accident' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id45skos:definition "See 'risk' (3).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id450skos:definition "[(i)<br/>
Loss of life or personal injury;<br/>
(ii) loss of or damage to property;<br/>
and each of the following to the extent determined by the law of the competent <br/>court:<br/>
(iii) economic loss arising from loss or damage referred to in sub-paragraph <br/>
(i) or (ii), insofar as not included in those sub-paragraphs, if incurred by a <br/>person entitled to claim in respect of such loss or damage;<br/>
(iv) the costs of measures of reinstatement of impaired environment, unless <br/>
such impairment is insignificant, if such measures are actually taken or to <br/>be taken, and insofar as not included in sub-paragraph (ii);<br/>
(v)<br/>
loss of income deriving from an economic interest in any use or <br/>enjoyment of the environment, incurred as a result of a significant <br/>impairment of that environment, and insofar as not included in sub-<br/>paragraph (ii);<br/>
(vi) the costs of 'preventive measures', and further loss or damage caused by <br/>
such measures;<br/>
(vii) any other economic loss, other than any caused by the impairment of the <br/>
environment, if permitted by the general law on civil liability of the <br/>competent court,<br/>
in the case of sub-paragraphs (i) to (v) and (vii) above, to the extent that the <br/>loss or damage arises out of or results from 'ionizing radiation' emitted by any <br/>'source' of 'radiation' inside a 'nuclear installation', or emitted from 'nuclear fuel' or <br/>'radioactive' products or 'waste' in, or of 'nuclear material 'coming from, originating <br/>in, or sent to, a 'nuclear installation', whether so arising from the <i>radioactive<br/></i>properties of such matter, or from a combination of 'radioactive' properties with <br/>toxic, explosive or other hazardous properties of such matter.] (From <br/>Ref. [25].)<br/>
In this context, <i><b>preventive measures</b></i> are defined as any reasonable measures <br/>taken by any person after a 'nuclear incident' has occurred to prevent or <br/>minimize damage referred to in sub-paragraphs (i) to (v) or (vii), subject to <br/>any 'approval' of the competent authorities 'required' by the law of the State <br/>where the measures were taken.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id451skos:definition "See 'emergency'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id452skos:definition "1. A 'facility' (including associated buildings and equipment) in which <br/>
'nuclear material' is produced, processed, used, handled, stored or disposed of.<br/>
See 'facilities and activities' and 'nuclear installation'.<br/>
See 'facilities and activities' and 'nuclear installation'.<br/>
2. [A 'facility' (including associated buildings and equipment) in which <br/>
'nuclear material' is produced, processed, used, handled, stored or disposed of, if <br/>damage to or interference with such 'facility' could lead to the release of <br/>significant amounts of 'radiation' or 'radioactive material'.] (From Ref. [30].) <br/>
<b>!</b> This usage is specific to the revised Convention on the Physical Protection of <br/>
Nuclear Material and Nuclear Facilities [30], for the purposes of the <br/>Convention, and should otherwise be avoided. (See http://www.iaea.org/<br/>NewsCenter/Features/PhysicalProtection/index.html)<br/>
3. [A civilian 'facility' and its associated land, buildings and equipment in <br/>
which 'radioactive materials' are produced, processed, used, handled, stored or <br/>disposed of on such a scale that consideration of 'safety' is 'required'.] (From <br/>Ref. [5].)<br/>
<b>!</b> This usage is specific to the Joint Convention on the Safety of Spent Fuel <br/>
Management and on the Safety of Radioactive Waste Management [5], for <br/>the purposes of the Joint Convention, and should otherwise be avoided.<br/>Essentially synonymous with 'authorized facility', and hence more general than <br/>'nuclear installation'. Note that this differs from safeguards terminology, in <br/>which 'installation' is more general than 'facility'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id453skos:definition "'Fissionable' 'nuclear material' in the form of fabricated elements for <br/>
loading into the reactor core of a civil nuclear power plant or 'research reactor'.<br/>
<i><b>fresh fuel.</b></i> 'New fuel' or 'unirradiated fuel', including 'fuel' fabricated from <br/>'fissionable' material recovered by 'reprocessing' previously irradiated 'fuel'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id454skos:definition "All 'operations' associated with the production of nuclear energy, <br/>
including:<br/>
(a)<br/>
Mining and processing of uranium or thorium ores;<br/>
(b)<br/>
Enrichment of uranium;<br/>
(c)<br/>
Manufacture of 'nuclear fuel';<br/>
(d)<br/>
'Operation' of nuclear reactors (including 'research reactors');<br/>
(e)<br/>
'Reprocessing' of 'spent fuel';<br/>
(f)<br/>
All 'waste management' 'activities' (including 'decommissioning') relating to <br/>'operations' associated with the production of nuclear energy; <br/>
(g)<br/>
Any related research and development 'activities'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id455skos:definition "See 'incident'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id456skos:definition "1. A 'nuclear fuel' fabrication plant, 'research reactor' (including subcritical <br/>
and 'critical assemblies'), nuclear power plant, 'spent fuel storage facility', <br/>enrichment plant or 'reprocessing' 'facility'. (From Ref. [1].)<br/>
This is essentially any 'authorized facilities' that are part of the <i>nuclear fuel <br/>cycle</i> except 'facilities' for the mining or processing of uranium or thorium ores <br/>and 'radioactive waste management facilities'.<br/>
2. [For each Contracting Party, any land based civil nuclear power plant <br/>
under its jurisdiction, including such 'storage', handling and 'treatment' <i>facilities<br/></i>for 'radioactive materials' as are on the same site and are directly related to the <br/>'operation' of the nuclear power plant. Such a plant ceases to be a <i>nuclear <br/>installation</i> when all 'nuclear fuel elements' have been removed permanently <br/>from the reactor core and have been stored safely in accordance with approved <br/>'procedures', and a 'decommissioning' programme has been agreed to by the <br/>'regulatory body'.] (From Ref. [4].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id457skos:definition "Plutonium except that with isotopic concentration exceeding 80% in <br/>
plutonium-238; uranium-233; 'uranium enriched in the isotope 235 or 233'; <br/>uranium containing the mixture of isotopes as occurring in nature other than in <br/>the form of ore or ore residue; any material containing one or more of the <br/>foregoing. (From Ref. [30].)<br/>
'Nuclear material' is necessary for the production of nuclear weapons or other <br/>nuclear explosive devices. Under comprehensive 'safeguards agreements', the <br/>IAEA verifies that all 'nuclear material' subject to safeguards has been <br/>declared and placed under safeguards. Certain non-nuclear materials are <br/>essential for the use or production of 'nuclear material' and may also be subject <br/>to IAEA safeguards under certain agreements.<br/>The Statute of the IAEA [31] uses the term <i><b>special fissionable material</b></i>, with <br/>the meaning essentially of 'nuclear material' as defined here, but explicitly <br/>excluding 'source material'.<br/>For the purposes of IAEA 'safeguards agreements', 'nuclear material' is defined <br/>as “any 'source material' or 'special fissionable material 'as defined in Article XX <br/>of the Statute of the IAEA”. The meaning is essentially the same as that of <br/>'nuclear material' as defined here. See Ref. [32].<br/>
The Paris Convention on Third Party Liability in the Field of Nuclear Energy <br/>[33] uses the term ‘nuclear substances’, which means 'nuclear fuel' (other than <br/>'natural uranium' and 'depleted uranium') and 'radioactive' products or <br/>'radioactive waste'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id458skos:definition "See 'emergency'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id459skos:definition "See 'sabotage'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id46skos:definition "See 'INES'.<br/>
See 'INES'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id460skos:definition "The achievement of proper 'operating conditions', prevention of 'accidents'<br/>
or mitigation of 'accident' consequences, resulting in 'protection' of 'workers', the <br/>public and the environment from undue 'radiation' hazards.<br/>
Often abbreviated to 'safety' in 'IAEA publications' on 'nuclear safety'. <i>Safety<br/></i>means 'nuclear safety' unless otherwise stated, in particular when other types of <br/>'safety' (e.g. fire 'safety', conventional industrial 'safety') are also being discussed. <br/>See 'protection and safety' for a discussion of the relationship between <i>nuclear <br/>safety</i> and 'radiation protection'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id461skos:definition "The prevention and detection of, and response to, theft, 'sabotage', <br/>
unauthorized access, illegal transfer or other 'malicious' acts involving <i>nuclear <br/>material</i>, other 'radioactive substances' or their associated 'facilities'.<br/>
See IAEA GOV/2005/50.<br/>This includes, but is not limited to, the prevention and detection of, and <br/>response to, the theft of 'nuclear material' or other 'radioactive material' (with or <br/>without knowledge of the nature of the material), 'sabotage', and other <br/>'malicious' acts, 'illicit trafficking' and unauthorized transfer.<br/>The response element of the definition refers to those actions aimed at <br/>‘reversing’ the immediate consequences of unauthorized access or actions <br/>(e.g. recovering material). Response to the radiological consequences that <br/>might ensue is considered part of 'safety'.<br/>Often abbreviated to 'security' in 'IAEA publications' on 'nuclear security'.<br/>There is not an exact distinction between the general terms 'safety' and 'security'. <br/>In general, 'security' is concerned with 'malicious' or negligent actions by <br/>humans that could cause or threaten harm to other humans; 'safety' is <br/>concerned with the broader issue of harm to humans (or the environment) <br/>
from 'radiation', whatever the cause. The precise interaction between <i>security<br/></i>and 'safety' depends on the context. 'Security' of 'nuclear material' for reasons <br/>relating to non-proliferation is outside the scope of the Safety Glossary.<br/>
Control<br/>
Measures<br/>
Safety<br/>
Security<br/>
Safety/Security<br/>
Synergies<br/>
'Safety' and 'security' 'synergies' concern, for example: the regulatory <br/>infrastructure; engineering provisions in the 'design' and 'construction' of <br/>'nuclear installations' and other 'facilities'; 'controls' on access to <i>nuclear <br/>installations</i> and other 'facilities'; the categorization of 'radioactive sources'; <br/>'source design'; the 'security' of the management of 'radioactive sources' and <br/>'radioactive material'; the recovery of 'orphan sources'; <i>emergency response<br/></i>plans; and 'radioactive' 'waste management'. 'Safety' matters are intrinsic to <br/>'activities', and transparent and probabilistic 'safety' 'analysis' is used. <i>Security<br/></i>matters concern 'malicious' actions and are confidential, and threat based <br/>judgement is used.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id462skos:definition "See 'terrorism'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id463skos:definition "See 'terrorism'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id464skos:definition "See 'illicit trafficking'.<br/>
See 'illicit trafficking'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id465skos:definition "See 'cause'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id466skos:definition "See 'exposure, types of'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id467skos:definition "Outside the 'site area'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id468skos:definition "Within the 'site area'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id469skos:definition "See 'plant states: operational states'.<br/>
See 'plant states: operational states'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id47skos:definition "See 'plant states'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id470skos:definition "See 'life'.<br/>
See 'life'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id471skos:definition "1. An organization applying for 'authorization' or 'authorized' to operate an <br/>
'authorized facility 'and responsible for its' safety'.<br/>
<b>!</b> Note that such an organization may become the 'operating organization' before <br/>
'operation' starts.<br/>In practice, for an 'authorized facility', the 'operating organization' is normally <br/>also the 'licensee' or 'registrant'. However, the separate terms are retained to <br/>refer to the two different capacities.<br/>See also 'operator'.<br/>
2. The organization (and its contractors) which undertakes the 'siting', <br/>
'design', 'construction', 'commissioning' and/or 'operation' of a 'nuclear facility'.<br/>
This usage is peculiar to 'waste safety' documentation, with the corresponding <br/>understanding of 'siting' as a multistage 'process'. This difference is partly a <br/>reflection of the particularly crucial role of 'siting' in the 'safety' of 'repositories'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id472skos:definition "See 'life: operating life/lifetime' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id473skos:definition "Individual 'workers' engaged in the 'operation' of an 'authorized facility'.<br/>
<b>!</b> This may be shortened to 'operator(s)', but only if there is no danger of <br/>
confusion with 'operator' in the sense of 'operating organization'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id474skos:definition "All 'activities' performed to achieve the purpose for which an 'authorized '<br/>
'facility' was constructed.<br/>
For a nuclear power plant, this includes 'maintenance', refuelling, <i>in-service <br/>inspection</i> and other associated 'activities'.<br/>
<i><b>abnormal operation.</b></i> See 'plant states:' 'anticipated operational occurrence'.<br/>
<i><b>assisted operation.</b></i> See 'assisted (by the IAEA) operation'.<br/>
The term ‘operation’ is used here in its normal sense.<br/>
<i><b>normal operation.</b></i> See 'plant states'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id475skos:definition "See 'bypass' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id476skos:definition "See 'level:' 'intervention level'.<br/>
See 'level:' 'intervention level'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id477skos:definition "See 'limit'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id478skos:definition "See 'life: operating life/lifetime' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id479skos:definition "See 'plant states'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id48skos:definition "For a nuclear reactor, an 'accident' for which the 'initiating event' is an <br/>
'anticipated operational occurrence' and in which the fast shutdown 'system' of the <br/>reactor fails to function.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id480skos:definition "See 'area'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id481skos:definition "See 'operations area'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id482skos:definition "Any organization or person applying for 'authorization' or authorized and/<br/>
or responsible for 'nuclear', 'radiation', 'radioactive waste' or 'transport safety' when <br/>undertaking 'activities' or in relation to any 'nuclear facilities' or 'sources' of <br/>'ionizing radiation'. This includes, inter alia, private individuals, governmental <br/>bodies, 'consignors' or 'carriers', 'licensees', hospitals, self-employed persons, etc.<br/>
<b>!</b> 'Operator' is sometimes used to refer to 'operating personnel'. If used in this way, <br/>
particular care should be taken to ensure that there is no possibility of <br/>confusion.<br/>'Operator' includes either those who are directly in 'control' of a 'facility' or an <br/>'activity' during use of a 'source' (such as radiographers or carriers) or, in the <br/>case of a 'source' not under 'control' (such as a lost or illicitly removed 'source' or <br/>a re-entering satellite), those who were responsible for the 'source' before <br/>'control' over it was lost.<br/>Synonymous with 'operating organization'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id483skos:definition "The 'process' of determining what level of 'protection and safety' makes <br/>
'exposure's, and the probability and magnitude of 'potential exposures', “as low as <br/>reasonably achievable, economic and social factors being taken into account” <br/>(<i><b>ALARA</b></i>), as required by the International Commission on Radiological <br/>Protection 'System of Radiological Protection'.<br/>
<b>!</b> This is not the same as optimization of the 'process' or 'practice' concerned. An <br/>
explicit term such as 'optimization' 'of' 'protection (and safety)' should be used.<br/>
<b>!</b> The <br/>
term <br/>
'ALARA' should not be used to mean 'optimization' 'of' 'protection '<br/>
'(and safety)'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id484skos:definition "See 'dose quantities'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id485skos:definition "See 'source' (2).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id486skos:definition "See 'emergency plan' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id487skos:definition "1. See 'waste management, radioactive' (1).<br/>
2. An enclosure such as a box or bag which is used by a single 'consignor'<br/>
to facilitate as a handling unit a 'consignment' of one or more 'packages' for <br/>convenience of handling, stowage and carriage. (From Ref. [2].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id488skos:definition "The 'packaging' with its 'radioactive contents' as presented for 'transport'. The <br/>
types of 'packages' covered by [the Transport] Regulations [2], which are subject <br/>to the 'activity limits' and material restrictions of Section IV [of the Transport <br/>Regulations [2]] and meet the corresponding 'requirements', are:<br/>
(a)<br/>
'Excepted package';<br/>
(b)<br/>
'Industrial package' Type 1 (Type IP-1);<br/>
(c)<br/>
'Industrial package' Type 2 (Type IP-2);<br/>
(d)<br/>
'Industrial package' Type 3 (Type IP-3);<br/>
(e)<br/>
'Type A package';<br/>
(f)<br/>
'Type B(U)' 'package';<br/>
(g)<br/>
'Type B(M) package';<br/>
(h)<br/>
'Type C package'.<br/>
'Packages' containing 'fissile material' or uranium hexafluoride are subject <br/>
to additional 'requirements'. (From Ref. [2].)<br/>
The detailed specifications and 'requirements' for these 'package' types are <br/>specified in Ref. [2], and are too complex to attempt to summarize here. <br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id489skos:definition "The product of 'conditioning' that includes the 'waste form' and any <br/>
'container(s)' and internal 'barriers' (e.g. absorbing materials and liner), as <br/>prepared in accordance with 'requirements' for handling, 'transport', 'storage' and/<br/>or 'disposal'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id49skos:definition "A 'legal person' who applies to a 'regulatory body' for 'authorization' to <br/>
undertake specified 'activities'.<br/>
Strictly, an 'applicant' would be such from the time at which an application is <br/>submitted until the requested 'authorization' is either granted or refused. <br/>However, the term is often used a little more loosely than this, particularly in <br/>cases where the 'authorization' 'process' is long and complex.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id490skos:definition "1. The assembly of 'components' necessary to enclose the 'radioactive '<br/>
'contents' completely. It may, in particular, consist of one or more receptacles, <br/>absorbent materials, spacing 'structures', 'radiation' shielding and service <br/>equipment for filling, emptying, venting and pressure relief; devices for cooling, <br/>absorbing mechanical shocks, handling and tie-down, and thermal insulation; <br/>and service devices integral to the 'package'. The 'packaging' may be a box, drum <br/>or similar receptacle, or may also be a 'freight container', 'tank' or <i>intermediate <br/>bulk container</i>. (From Ref. [2].)<br/>
2. See 'waste management, radioactive' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id491skos:definition "See 'fluence'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id492skos:definition "See 'aircraft'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id493skos:definition "A 'component' whose functioning does not depend on an external input <br/>
such as actuation, mechanical movement or supply of power.<br/>
A 'passive component' has no moving part, and, for example, only experiences <br/>a change in pressure, in temperature or in fluid flow in performing its <br/>functions. In addition, certain 'components' that function with very high <br/>'reliability' based on irreversible action or change may be assigned to this <br/>category.<br/>Examples of 'passive components' are heat exchangers, pipes, vessels, electrical <br/>cables and 'structures'. It is emphasized that this definition is necessarily <br/>general in nature, as is the corresponding definition of 'active component'. <br/>Certain 'components', such as rupture discs, check valves, 'safety' valves, <br/>injectors and some solid state electronic devices, have characteristics which <br/>require special consideration before designation as an 'active' or <i>passive <br/>component</i>.<br/>Any 'component' that is not a 'passive component' is an 'active component'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id494skos:definition "An examination or review of commercial, professional or academic <br/>
efficiency, competence, etc., by others in the same occupation.<br/>
Also: The evaluation, by experts in the relevant field, of a scientific research <br/>project for which a grant is sought; the 'process' by which a learned journal <br/>passes a paper received for publication to outside experts for their comments <br/>on its suitability and worth; refereeing.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id495skos:definition "See 'assessment' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id496skos:definition "See 'indicator'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id497skos:definition "See 'maintenance'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id498skos:definition "A systematic reassessment of the 'safety' of an existing 'facility (or activity)'<br/>
carried out at regular intervals to deal with the cumulative effects of 'ageing', <br/>modifications, operating experience, technical developments and 'siting' aspects, <br/>and aimed at ensuring a high level of 'safety' throughout the 'service life' of the <br/>'facility (or activity)'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id499skos:definition "See 'relocation'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id5skos:definition "The fraction of energy emitted as a specified 'radiation' type in a specified <br/>
'source region' that is absorbed in a specified 'target tissue'.<br/>
4 Of Ref. [2].<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id50skos:definition "The granting of consent by a 'regulatory body.'<br/>
Typically used to represent any form of consent from the 'regulatory body' that <br/>does not meet the definition of 'authorization'. However, the usage in the <br/>Transport Regulations [2] (see 'multilateral approval' and 'unilateral approval'<br/>
below — the term 'approval' is not separately defined) is that 'approval' is <br/>essentially synonymous with 'authorization'.<br/>
<i><b>multilateral approval.</b></i> 'Approval' by the relevant 'competent authority' of <br/>the 'country of origin' of the 'design' or 'shipment', as applicable, and also, <br/>where the 'consignment' is to be transported through or into any other <br/>country, 'approval' by the 'competent authority' of that country. The term <br/>‘through or into’ specifically excludes ‘over’, i.e. the 'approval' and <br/>'notification' 'requirements' shall not apply to a country over which <br/>'radioactive material' is carried in an 'aircraft', provided that there is no <br/>scheduled stop in that country. (From Ref. [2].)<br/>
<i><b>unilateral approval.</b></i> An 'approval' of a 'design' which is 'required' to be <br/>given by the 'competent authority' of the 'country of origin' of the <i>design<br/></i>only. (From Ref. [2].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id500skos:definition "See 'dose equivalent quantities'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id501skos:definition "See 'monitoring' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id502skos:definition "See 'monitoring' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id503skos:definition "See 'ageing'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id504skos:definition "See 'diversity'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id505skos:definition "See 'half-life' (2): 'radioactive half-life'.<br/>
See 'half-life' (2): 'radioactive half-life'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id506skos:definition "See 'protection' (3).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id507skos:definition "Separation by geometry (distance, orientation, etc.), by appropriate <br/>
'barriers', or by a combination thereof.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id508skos:definition "See 'sorption'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id509skos:definition "See 'maintenance'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id51skos:definition "<i><b>controlled area.</b></i> A defined area in which specific 'protection' measures and <br/>'safety' provisions are or could be 'required' for controlling <i>normal <br/>exposures</i> or preventing the spread of 'contamination' during normal <br/>working conditions, and preventing or limiting the extent of <i>potential <br/>exposures</i>.<br/>
A 'controlled area' is often within a 'supervised area', but need not be.<br/>The term <i><b>radiation area</b></i> is sometimes used to describe a similar concept, but <br/>'controlled area' is preferred in 'IAEA publications'.<br/>
<i><b>operations area.</b></i> A geographical area that contains an 'authorized facility'. <br/>It is enclosed by a physical 'barrier' (the <i><b>operations boundary</b></i>) to prevent <br/>unauthorized access, by means of which the management of the <br/>'authorized facility' can exercise direct authority.<br/>
This applies to larger 'facilities'.<br/>
<b>['radiation area'</b><b>]'.'</b> See 'controlled area'.<br/>
<i><b>site area.</b></i> A geographical area that contains an <i>authorized facility, <br/>authorized activity </i>or' source', and within which the management of the <br/>'authorized facility 'or 'authorized activity' may directly initiate <i>emergency <br/>actions</i>.<br/>
This is typically the area within the 'security' perimeter fence or other <br/>designated property marker. It may also be the 'controlled area' around a <br/>
radiography 'source' or a cordoned off area established by <i>first responders<br/></i>around a suspected hazard.<br/>This area is often identical to the 'operations area', except in situations (e.g. <br/>'research reactors', 'irradiation installations') where the' authorized facility 'is on a <br/>site where other 'activities' are being carried out beyond the 'operations area', <br/>but where the management of the 'authorized facility' can be given some <br/>degree of authority over the whole 'site area'.<br/>The <i><b>site boundary</b></i> is the boundary of the 'site area'.<br/>The term 'activity' is used here in the sense of 'activity' (2).<br/>
<i><b>supervised area.</b></i> A defined area not designated a 'controlled area' but for <br/>which 'occupational exposure' conditions are kept under review, even <br/>though no specific 'protection' measures or 'safety' provisions are normally <br/>needed.<br/>
See also 'controlled area'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id510skos:definition "Plant equipment <br/>
Items important to safetya<br/>
Items not important to safetya<br/>
Safety related itemsa<br/>
Safety systems<br/>
Protection<br/>
Safety actuation<br/>
Safety system<br/>
system<br/>
system<br/>
support features<br/>
a<br/>
In this context, an ‘item’ is a 'structure', 'system' or 'component'.<br/>
<i><b>item important to safety.</b></i> An item that is part of a 'safety group' and/or <br/>whose malfunction or 'failure' could lead to 'radiation exposure' of the <i>site <br/>personnel</i> or 'members of the public'.<br/>
'Items important to safety' include:<br/>
— Those' structures, systems and components' whose malfunction or 'failure' could <br/>
lead to undue 'radiation exposure' of 'site personnel' or 'members of the public';<br/>
— Those' structures, systems and components' that prevent 'anticipated operational '<br/>
'occurrences' from leading to 'accident conditions';<br/>
— Those features that are provided to mitigate the consequences of malfunction <br/>
or 'failure' of 'structures, systems and components'.<br/>
<i><b>protection system.</b></i> 'System' that monitors the 'operation' of a reactor and <br/>which, on sensing an abnormal condition, automatically initiates actions <br/>to prevent an unsafe or potentially unsafe condition.<br/>
<b>!</b> This use of the term 'protection' refers to 'protection' of the plant ('protection'<br/>
(2)).<br/>The 'system' in this case encompasses all electrical and mechanical devices and <br/>circuitry, from sensors to 'actuation device' input terminals.<br/>
<i><b>safety actuation system.</b></i> The collection of equipment required to <br/>accomplish the necessary 'safety actions' when initiated by the <i>protection <br/>system</i>.<br/>
<i><b>safety related item.</b></i> An 'item important to safety' that is not part of a <i>safety <br/>system</i>.<br/>
<i><b>safety related system.</b></i> A 'system' important to 'safety 'that is not part of a <br/>'safety system'.<br/>
A 'safety' related instrumentation and 'control' 'system', for example, is an <br/>instrumentation and 'control' 'system' that is important to 'safety' but which is not <br/>part of a 'safety system'.<br/>
<i><b>safety system.</b></i> A 'system' important to 'safety', provided to ensure the safe <br/>shutdown of the reactor or the 'residual heat' removal from the core, or to <br/>limit the consequences of 'anticipated operational occurrences' and <i>design <br/>basis accidents</i>.<br/>
'Safety systems' consist of the 'protection system', the 'safety actuation systems' and <br/>the 'safety system support features'. 'Components' of 'safety systems' may be <br/>provided solely to perform 'safety functions', or may perform 'safety functions' in <br/>some plant 'operational states' and non-safety functions in other <i>operational <br/>states</i>.<br/>
<i><b>safety system support features.</b></i> The collection of equipment that provides <br/>services such as cooling, lubrication and energy supply required by the <br/>'protection system' and the 'safety actuation systems'.<br/>
<b>!</b> After <br/>
a <br/>
'postulated initiating event', some required 'safety system support '<br/>
'features' may be initiated by the 'protection system' and others may be initiated <br/>by the 'safety actuation systems' they serve; other required <i>safety system support <br/>features</i> may not need to be initiated if they are in 'operation' at the time of the <br/>'postulated initiating event'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id511skos:definition "Operational states<br/>
Accident conditions<br/>
Within design basis<br/>
Beyond design basis<br/>
accidents<br/>
accidents<br/>
Anticipated<br/>
Design<br/>
Normal<br/>
operational<br/>
basis<br/>
Severe<br/>
operation<br/>
a<br/>
b<br/>
occurrences<br/>
accidents<br/>
accidents<br/>
Accident management<br/>
a<br/>
'Accident conditions' that are not 'design basis accidents' as explicitly considered but<br/>which are encompassed by them.<br/>
b<br/>
'Beyond design basis accidents' without significant core degradation.<br/>
This figure differs from that in the 1988 versions of the Nuclear Safety <br/>Standards Codes, as follows:<br/>(a) 'Accident conditions' are now taken to include all non-operational states, <br/>
rather than just 'design basis accidents' and those conditions encompassed <br/>by them (marked a);<br/>
(b) The new category, marked b, of 'beyond design basis accidents' that are not <br/>
classified as 'severe accidents' because there is no significant core <br/>degradation;<br/>
(c) The term 'accident management' is applied only to 'beyond design basis '<br/>
'accidents', rather than to all non-operational states.<br/>
<i><b>accident conditions.</b></i> 'Deviations' from 'normal operation' more severe than <br/>'anticipated operational occurrences', including 'design basis accidents' and <br/>'severe accidents'.<br/>
Examples of such 'deviations' include a major 'fuel failure' or a loss of coolant <br/>accident (LOCA).<br/>See 'accident'.<br/>
<i><b>accident management.</b></i> The taking of a set of actions during the evolution <br/>of a 'beyond design basis accident':<br/>
(a) To prevent the escalation of the 'event' into a 'severe accident';<br/>(b) To mitigate the consequences of a 'severe accident';<br/>(c) To achieve a long term safe stable state.<br/>
The second aspect of 'accident management' (to mitigate the consequences of a <br/>'severe accident') is also termed 'severe accident management'.<br/>
<i><b>anticipated operational occurrence.</b></i> An operational 'process' deviating <br/>from 'normal operation' which is expected to occur at least once during the <br/>'operating lifetime' of a 'facility' but which, in view of appropriate <i>design<br/></i>provisions, does not cause any significant damage to <i>items important to <br/>safety</i> or lead to 'accident conditions'.<br/>
Examples of 'anticipated operational occurrences' are loss of normal electrical <br/>power and faults such as a turbine trip, malfunction of individual items of a <br/>normally running plant, 'failure' to function of individual items of <i>control<br/></i>equipment, and loss of power to the main coolant pump.<br/>Some States and organizations use the term <i><b>abnormal operation</b></i> (for contrast <br/>with 'normal operation') for this concept.<br/>
<i><b>beyond design basis accident.</b></i> 'Accident conditions' more severe than a <br/>'design basis accident'.<br/>
<i><b>design basis accident.</b></i> 'Accident conditions' against which a 'facility' is <br/>designed according to established 'design' criteria, and for which the <br/>damage to the 'fuel' and the release of 'radioactive material' are kept within <br/>'authorized limits'.<br/>
<i><b>normal operation.</b></i> 'Operation' within specified <i>operational limits and <br/>conditions</i>.<br/>
For a nuclear power plant, this includes startup, power 'operation', shutting <br/>down, shutdown, 'maintenance', testing and refuelling.<br/>
<i><b>operational states.</b></i> States defined under 'normal operation' and <i>anticipated <br/>operational occurrences</i>.<br/>
Some States and organizations use the term <i><b>operating conditions</b></i> (in contrast <br/>to 'accident conditions') for this concept.<br/>
<i><b>severe accident.</b></i> 'Accident conditions' more severe than a <i>design basis <br/>accident</i> and involving significant core degradation.<br/>
<i><b>severe accident management.</b></i> See 'severe accident' and <i>accident <br/>management</i>.<br/>
By extension, 'accident management' for a 'severe accident' includes the taking of <br/>a set of actions during the evolution of the 'accident' to mitigate degradation of <br/>the core.<br/>
<i><b>within design basis accident.</b></i> 'Accident conditions' not more severe than a <br/>'design basis accident'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id512skos:definition "A substance used to reduce 'reactivity' in a reactor core, by virtue of its <br/>
high neutron 'absorption' cross-section.<br/>
<b>['burnable poison'</b><b>]'.'</b> A 'poison' that becomes less effective as a result of <br/>absorbing neutrons.<br/>
<b>!</b> The <br/>
term <br/>
'burnable absorber' is preferred.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id513skos:definition "See 'initiating event'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id514skos:definition "The total alpha energy ultimately emitted during the decay of 'radon '<br/>
'progeny' or of 'thoron progeny' through the decay chain.<br/>
<b>!</b> Note that the definition of 'radon progeny' includes the decay chain up to but <br/>
not including lead-210.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id515skos:definition "The time integral of the 'potential alpha energy' concentration in air over <br/>
the time period for which an individual is exposed to 'radon progeny' or <i>thoron <br/>progeny</i>.<br/>
<b>!</b> This is not a form of 'potential exposure'.<br/>
Used in measuring 'exposure' to 'radon progeny' and 'thoron progeny', <br/>particularly for 'occupational exposure'.<br/>Unit: J·h/m3.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id516skos:definition "See 'exposure situations'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id517skos:definition "Any human activity that introduces additional 'sources' of 'exposure' or <br/>
additional 'exposure pathways', or extends 'exposure' to additional people, or <br/>modifies the network of 'exposure pathways' from existing 'sources', so as to <br/>increase the 'exposure' or the likelihood of 'exposure' of people or the number of <br/>people exposed. (From Ref. [1].)<br/>
<b>!</b> 'Radioactive waste' is generated as a result of 'practices' that involve some <br/>
beneficial effect, such as the generation of electricity by nuclear means or the <br/>diagnostic application of radioisotopes. The management of this 'waste' is <br/>therefore only one part of the overall 'practice'.<br/>Contrasting term: 'intervention'. See also 'facilities and activities'.<br/>Terms such as ‘authorized 'practice'’, ‘controlled 'practice'’ and ‘regulated <br/>'practice'’ are used to distinguish those 'practices' that are subject to <i>regulatory <br/>control</i> from other 'activities' which meet the definition of a 'practice' but do not <br/>need or are not amenable to 'control'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id518skos:definition "See 'emergency zones'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id519skos:definition "See 'maintenance'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id52skos:definition "See 'monitoring' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id520skos:definition "See 'waste management, radioactive' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id521skos:definition "See 'limit'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id522skos:definition "See 'waste management, radioactive' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id523skos:definition "See 'maintenance'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id524skos:definition "See ['nuclear damage'].<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id525skos:definition "See 'limit'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id526skos:definition "A 'component' that converts energy into action when commanded by an <br/>
'actuation device'.<br/>
Such as a motor, solenoid operator or pneumatic operator.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id527skos:definition "Often taken to be synonymous with <i><b>stochastic analysis</b></i>. Strictly, however, <br/>'stochastic' conveys directly the idea of randomness (or at least apparent <br/>randomness), whereas 'probabilistic' is directly related to probabilities, and <br/>hence only indirectly concerned with randomness. Therefore, a natural <i>event<br/></i>or 'process' might more correctly be described as 'stochastic' (as in <i>stochastic <br/>effect</i>), whereas 'probabilistic' would be more appropriate for describing a <br/>mathematical 'analysis' of 'stochastic' 'events' or 'processes' and their consequences <br/>(such an 'analysis' would, strictly, only be 'stochastic' if the analytical method <br/>itself included an element of randomness, e.g. Monte Carlo 'analysis').<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id528skos:definition "A comprehensive, structured approach to identifying 'failure' 'scenarios', <br/>
constituting a conceptual and mathematical tool for deriving numerical <br/>estimates of 'risk'.<br/>
Three levels of 'probabilistic safety assessment' are generally recognized. Level 1 <br/>comprises the 'assessment' of plant 'failur'es leading to determination of the <br/>frequency of core damage. Level 2 includes the 'assessment' of <i>containment<br/></i>response, leading, together with Level 1 results, to the determination of <br/>frequencies of 'failure' of the 'containment' and release to the environment of a <br/>given percentage of the reactor core’s inventory of radionuclides. Level 3 includes <br/>the 'assessment' of 'off-site' consequences, leading, together with the results of Level <br/>2 'analysis', to estimates of public 'risks'. (See, for example, Ref. [34].)<br/>
<i><b>living probabilistic safety assessment.</b></i> A 'probabilistic safety assessment' that <br/>is updated as necessary to reflect the current 'design' and operational features, <br/>and is documented in such a way that each aspect of the 'PSA' 'model' can be <br/>directly related to existing plant information, plant documentation or the <br/>analysts’ assumptions in the absence of such information.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id529skos:definition "A series of specified actions conducted in a certain order or manner. <br/>
The set of actions to be taken to conduct an activity or to perform a 'process' is <br/>typically specified in a set of instructions.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id53skos:definition "See 'survey'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id530skos:definition "1. A course of action or proceeding, especially a series of progressive <br/>
stages in the manufacture of a product or some other 'operation'.<br/>
2. A set of interrelated or interacting 'activities' that transforms inputs into <br/>
outputs.<br/>
A product is the result or output of a 'process'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id531skos:definition "See 'waste management, radioactive' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id532skos:definition "See 'dose concepts'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id533skos:definition "See 'exposure situations:' 'chronic exposure'.<br/>
See 'exposure situations:' 'chronic exposure'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id534skos:definition "1. (against 'radiation'):<br/>
<i><b>radiation protection</b></i> (also <i><b>radiological protection</b></i>). The 'protection' of <br/>people from the effects of 'exposure' to 'ionizing radiation', and the means <br/>for achieving this.<br/>
See also 'protection and safety'.<br/>The International Commission on Radiological Protection and others use the <br/>term 'radiological protection', which is synonymous.<br/>The accepted understanding of the term 'radiation protection' is restricted to <br/>'protection' of humans. Suggestions to extend the definition to include the <br/>'protection' of non-human species or the environment are controversial.<br/>
2. (of a nuclear reactor). See 'plant equipment: protection system'.<br/>
3. (of 'nuclear material'):<br/>
[<i><b>physical protection.</b></i> Measures for the 'protection' of 'nuclear material' or <br/>'authorized facilities', designed to prevent unauthorized access or removal <br/>of 'fissile material' or 'sabotage' with regard to safeguards, as, for example, in <br/>the Convention on the Physical Protection of Nuclear Material.] [30]<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id535skos:definition "The 'protection' of people against 'exposure' to 'ionizing radiation' or <br/>
'radioactive materials' and the 'safety' of 'radiation' 'sources', including the means for <br/>achieving this, and the means for preventing 'accidents' and for mitigating the <br/>consequences of 'accidents' should they occur. (From Ref. [1].)<br/>
'Safety' is primarily concerned with maintaining 'control' over 'sources', whereas <br/>'(radiation) protection' is primarily concerned with controlling 'exposure' to <br/>'radiation' and its effects. Clearly the two are closely connected: <i>radiation <br/>protection</i> (or 'radiological protection') is very much simpler if the 'source' in <br/>question is under 'control', so 'safety' necessarily contributes towards 'protection'. <br/>'Sources' come in many different types, and hence 'safety' may be termed <br/>'nuclear safety',' radiation safety', 'radioactive waste safety' or 'transport' 'safety', but <br/>'protection' (in this sense) is primarily concerned with protecting humans <br/>against 'exposure', whatever the 'source', and so is always 'radiation protection'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id536skos:definition "See 'plant equipment'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id537skos:definition "1. An 'intervention' intended to avoid or reduce 'doses' to 'members of the '<br/>
'public' in 'emergencies' or situations of 'chronic exposure'.<br/>
See also 'remedial action'.<br/>This is related to 'radiation protection' (see definition (1) of 'protection', and <br/>'protection and safety').<br/>
<i><b>longer term protective action.</b></i> A 'protective action' that is not an <i>urgent <br/>protective action</i>.<br/>
Such 'protective actions' are likely to be prolonged over weeks, months or <br/>years.<br/>These include measures such as 'relocation', 'agricultural countermeasures' and <br/>'remedial actions'.<br/>
<i><b>mitigatory action.</b></i> Immediate action by the 'operator' or other party:<br/>
(1) To reduce the potential for conditions to develop that would result in <br/>
'exposure' or a release of 'radioactive material' requiring <i>emergency <br/>actions</i> on or off the site; or<br/>
(2) To mitigate 'source' conditions that may result in 'exposure' or a release <br/>
of 'radioactive material' requiring 'emergency actions' on or off the site.<br/>
<i><b>urgent protective action.</b></i> A 'protective action' in the event of an <i>emergency <br/></i>which must be taken promptly (normally within hours) in order to be <br/>effective, and the effectiveness of which will be markedly reduced if it is <br/>delayed.<br/>
The most commonly considered 'urgent protective actions' in a <i>nuclear or <br/>radiological emergency</i> are 'evacuation', 'decontamination' of individuals, <br/>'sheltering', respiratory 'protection', 'iodine prophylaxis' and restriction of the <br/>consumption of potentially contaminated foodstuffs. <br/>
2. A 'protection system' action calling for the 'operation' of a particular <br/>
'safety' 'actuation device'.<br/>
This is related to definition (2) of 'protection'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id538skos:definition "The generation of at least those 'protective actions' necessary to ensure that <br/>
the 'safety task' required by a given 'postulated initiating event' is accomplished.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id539skos:definition "See 'exposure, types of'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id54skos:definition "See 'emergency response arrangements'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id540skos:definition "See 'IAEA publication'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id541skos:definition "<i><b>equipment qualification.</b></i> Generation and 'maintenance' of evidence to <br/>ensure that equipment will operate on demand, under specified <i>service <br/>conditions</i>, to meet 'system' performance requirements.<br/>
See Ref. [9].<br/>More specific terms are used for particular equipment or particular <br/>conditions; for example, <i><b>seismic qualification</b></i> is a form of <i>equipment <br/>qualification</i> that relates to conditions that could be encountered in the event <br/>of earthquakes.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id542skos:definition "Equipment certified as having satisfied 'equipment qualification'<br/>
requirements for the conditions relevant to its 'safety function(s)'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id543skos:definition "An individual who, by virtue of certification by appropriate boards or <br/>
societies, professional licences or academic qualifications and experience, is <br/>duly recognized as having expertise in a relevant field of specialization, e.g. <br/>medical physics, 'radiation protection', occupational health, fire safety, <i>quality <br/>assurance</i> or any relevant engineering or 'safety' speciality. (From Ref. [1].)<br/>
This should not normally need definition.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id544skos:definition "See 'life'.<br/>
See 'life'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id545skos:definition "1. The function of a 'management system' that provides confidence that <br/>
specified 'requirements' will be fulfilled.<br/>
<b>!</b> The IAEA is revising the 'requirements' and guidance in the subject area of <br/>
'quality assurance' for new 'safety standards' on 'management systems' for the <br/>'safety' of nuclear 'facilities and activities' involving the use of 'ionizing radiation'. <br/>The term 'management system' has been adopted in the revised standards <br/>instead of the terms 'quality assurance' and ‘'quality' 'assurance' programme’.<br/>Planned and systematic actions are necessary to provide adequate confidence <br/>that an item, 'process' or service will satisfy given 'requirements' for quality; for <br/>
example, those specified in the 'licence'. This statement is slightly modified <br/>from that in ISO 921:1997 (Nuclear Energy: Vocabulary) [7] to say ‘an item, <br/>'process' or service’ instead of ‘a product or service’ and to add the example. A <br/>more general definition of 'quality assurance' and definitions of related terms <br/>can be found in ISO 8402:1994 [35].<br/>
2. A systematic programme of 'controls' and 'inspections' applied by any <br/>
organization or body involved in the 'transport' of 'radioactive material' which is <br/>aimed at providing adequate confidence that the standard of 'safety' prescribed <br/>in [the Transport] Regulations is achieved in practice. (From Ref. [2].)<br/>
3. All those planned and systematic actions necessary to provide <br/>
confidence that a 'structure, system or component' will perform satisfactorily in <br/>service. (From Ref. [35].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id546skos:definition "Part of 'quality assurance' intended to verify that 'structures, systems and '<br/>
'components' correspond to predetermined requirements.<br/>
This definition is taken from ISO 921:1997 (Nuclear Energy: Vocabulary) [7]. <br/>A more general definition of 'quality control' and definitions of related terms <br/>can be found in ISO 8402:1994 [35].<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id547skos:definition "A number by which the 'absorbed dose' in a tissue or organ is multiplied to <br/>
reflect the 'relative biological effectiveness' of the 'radiation', the result being the <br/>'dose equivalent'.<br/>
Superseded by 'radiation weighting factor' in the definition of <i>equivalent dose<br/></i>in Ref. [16], but still defined, as a function of 'linear energy transfer', for use in <br/>calculating the 'dose equivalent quantities 'used in' monitoring'. The BSS [1] also <br/>
'—'<br/>
state that the mean 'quality factor Q 'at 10 mm depth in the 'ICRU sphere' can <br/>be used as a value of 'radiation weighting factor' for 'radiation' types for which <br/>the BSS do not specify a value (see 'radiation weighting factor').<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id548skos:definition "Unit of 'absorbed dose', equal to 0.01 Gy.<br/>
Superseded by the 'gray (Gy)'.<br/>Abbreviation of 'röntgen absorbed dose' or 'radiation absorbed dose'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id549skos:definition "<b>!</b> When <br/>
used <br/>
in <br/>
'IAEA publications', the term 'radiation' normally refers only to <br/>
'ionizing radiation'. The IAEA has no statutory responsibilities in relation to <br/>non-ionizing 'radiation'.<br/>'Ionizing radiation' can be divided into 'low linear energy transfer radiation' and <br/>'high linear energy transfer radiation' (as a guide to its <i>relative biological <br/>effectiveness</i>), or into 'strongly penetrating radiation' and <i>weakly penetrating <br/>radiation</i> (as an indication of its ability to penetrate shielding or the human <br/>body).<br/>
<i><b>high linear energy transfer radiation.</b></i> 'Radiation' with high <i>linear energy <br/>transfer</i>, normally assumed to comprise protons, neutrons and alpha <br/>particles (or other particles of similar or greater mass).<br/>
These are the types of 'radiation' for which the International Commission on <br/>Radiological Protection recommends a 'radiation weighting factor' greater <br/>than 1.<br/>Contrasting term: 'low linear energy transfer radiation'.<br/>
<i><b>ionizing radiation.</b></i> For the purposes of 'radiation protection', <i>radiation<br/></i>capable of producing ion pairs in biological material(s). (From Ref. [1].)<br/>
<i><b>low linear energy transfer radiation.</b></i> 'Radiation' with low <i>linear energy <br/>transfer</i>, normally assumed to comprise photons (including X rays and <br/>gamma 'radiation'), electrons, positrons and muons.<br/>
These are the types of 'radiation' for which the International Commission on <br/>Radiological Protection recommends a 'radiation weighting factor' of 1.<br/>
<i><b>strongly penetrating radiation.</b></i> 'Radiation' for which 'limits' on <i>effective <br/>dose</i> are normally more restrictive than 'limits' on 'equivalent dose' to any <br/>tissue or organ, i.e. the fraction of the relevant 'dose limit' received will, for <br/>a given 'exposure', be higher for 'effective dose' than for 'equivalent dose' to <br/>any tissue or organ. If the reverse is true, the 'radiation' is termed <i><b>weakly <br/>penetrating radiation</b></i>.<br/>
For most practical purposes, it may be assumed that <i>strongly penetrating <br/>radiation</i> includes photons of energy above about 20–30 keV, high energy <br/>electrons (more than about 1–2 MeV) and neutrons, and that <i>weakly <br/>penetrating radiation</i> includes photons of energy below about 20–30 keV, beta <br/>particles and other electrons of less than about 1–2 MeV, and massive charged <br/>particles such as protons.<br/>Contrasting term: 'weakly penetrating radiation'.<br/>
<i><b>weakly penetrating radiation.</b></i> See 'radiation:' <i>strongly penetrating <br/>radiation</i>.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id55skos:definition "1. The 'process', and the result, of analysing systematically and evaluating <br/>
the hazards associated with 'sources' and 'practices', and associated <i>protection and <br/>safety </i>measures.<br/>
'Assessment' is often aimed at quantifying performance measures for <br/>comparison with criteria.<br/>In 'IAEA publications', 'assessment' should be distinguished from 'analysis'. <br/>'Assessment' is aimed at providing information that forms the basis of a <br/>decision on whether or not something is satisfactory. Various kinds of <i>analysis<br/></i>may be used as tools in doing this. Hence an 'assessment' may include a number <br/>of 'analyses'.<br/>
<i><b>consequence assessment.</b></i> 'Assessment' of the radiological consequences <br/>(e.g. 'doses', 'activity concentrations')6 of 'normal operation' and possible <br/>'accidents' associated with an 'authorized facility' or part thereof.<br/>
This differs from 'risk assessment' in that probabilities are not included in the <br/>'assessment'.<br/>
<i><b>dose assessment.</b></i> 'Assessment' of the 'dose(s)' to an individual or group of <br/>people.<br/>
For example, 'assessment' of the 'dose' received by or 'committed' to by an <br/>individual on the basis of results from 'workplace monitoring' or 'bioassay'.<br/>The term 'exposure assessment' is also sometimes used.<br/>
<i><b>exposure assessment.</b></i> See 'assessment '(1),' dose assessment'.<br/>
<i><b>performance assessment.</b></i> 'Assessment' of the performance of a 'system' or <br/>subsystem and its implications for 'protection and safety' at an <i>authorized <br/>facility</i>.<br/>
This differs from 'safety assessment' in that it can be applied to parts of an <br/>'authorized facility' (and its environment), and does not necessarily require the <br/>'assessment' of radiological impacts.<br/>
<i><b>risk assessment.</b></i> 'Assessment' of the radiological 'risks' associated with <br/>'normal operation' and possible 'accidents' involving a 'source' or 'practice'.<br/>
This will normally include 'consequence assessment', together with some <br/>'assessment' of the probability of those consequences arising.<br/>
<i><b>safety assessment.</b></i> 1. 'Assessment' of all aspects of a 'practice' that are <br/>relevant to 'protection and safety';' 'for an 'authorized facility', this includes <br/>'siting', 'design' and 'operation' of the 'facility'.<br/>
This will normally include 'risk assessment'.<br/>See also 'probabilistic safety assessment (PSA)'.<br/>
6 Care should be taken when discussing ‘consequences’ in this context to <br/>
distinguish between radiological consequences of events causing 'exposure', such as 'doses', <br/>and the health consequences, such as cancers, that could result from 'doses'. <br/>‘Consequences’ of the former type generally imply a probability of experiencing <br/>‘consequences’ of the latter type. See also 'end point'.<br/>
2. 'Analysis' to predict the performance of an overall 'system' and its <br/>impact, where the performance measure is the radiological impact or <br/>some other global measure of the impact on 'safety'.<br/>
3. The systematic 'process' that is carried out throughout the <i>design<br/>process</i> to ensure that all the relevant 'safety requirements' are met by the <br/>proposed (or actual) 'design'. 'Safety assessment' includes, but is not limited <br/>to, the formal 'safety analysis'.<br/>
See Ref. [9].<br/>
<i><b>threat assessment.</b></i> The 'process' of analysing systematically the hazards <br/>associated with 'facilities', 'activities' or 'sources' within or beyond the borders <br/>of a State in order to identify:<br/>
(a) Those 'events' and the associated areas for which 'protective actions' may <br/>
be 'required' within the State;<br/>
(b) The actions that would be effective in mitigating the consequences of <br/>
such 'events'.<br/>The term 'threat assessment' does not imply that any threat, in the sense of an <br/>intention and capability to cause harm, has been made in relation to such <br/>'facilities', 'activities' or 'sources'.<br/>
2.' Activities' carried out to determine that 'requirements' are met and that <br/>
'processes' are adequate and effective, and to encourage managers to implement <br/>improvements, including 'safety' improvements.<br/>
This usage originated in 'quality assurance' and related fields.<br/>
<b>!</b> The IAEA is revising the 'requirements' and guidance in the subject area of <br/>
'quality assurance' for new 'safety standards' on 'management systems' for the <br/>'safety' of nuclear 'facilities and activities' involving the use of 'ionizing radiation'. <br/>The term 'management system' has been adopted in the revised standards <br/>instead of the terms 'quality assurance' and 'quality assurance' programme.<br/>'Assessment' 'activities' may include reviewing, checking, inspecting, testing, <br/>surveillance, auditing, peer evaluation and technical review. These <i>activities<br/></i>can be divided into two broad categories: 'independent assessment' and <br/>'self-assessment'.<br/>
<i><b>independent assessment.</b></i> 'Assessments' such as 'audits' or surveillances <br/>carried out to determine the extent to which the 'requirements' for the <br/>'management system' are fulfilled, to evaluate the effectiveness of the <br/>'management system' and to identify opportunities for improvement. They <br/>can be conducted by or on behalf of the organization itself for internal <br/>
purposes, by interested parties such as customers and regulators (or by <br/>other persons on their behalf), or by external independent organizations.<br/>
This definition applies in 'management systems' and related fields.<br/>Persons conducting 'independent assessments' do not participate directly in the <br/>work being assessed.<br/>'Independent assessment' 'activities' include internal and external 'audit', <br/>surveillance, peer evaluation and technical review, which are focused on <i>safety<br/></i>aspects and areas where problems have been found.<br/>An 'audit' is used in the sense of a documented activity performed to <br/>determine by investigation, examination and evaluation of objective evidence <br/>the adequacy of, and adherence to, established 'procedures', instructions, <br/>specifications, codes, standards, administrative or operational programmes <br/>and other applicable documents, and the effectiveness of their <br/>implementation.<br/>
<i><b>self-assessment.</b></i> A routine and continuing 'process' conducted by <i>senior <br/>management</i> and management at other levels to evaluate the <br/>effectiveness of performance in all areas of their responsibility.<br/>
This definition applies in 'management systems' and related fields.<br/>'Self-assessment' 'activities' include review, surveillance and discrete checks, <br/>which are focused on preventing, or identifying and correcting, management <br/>problems that hinder the achievement of the organization’s objectives, <br/>particularly 'safety' objectives.<br/>'Self-assessment' provides an overall view of the performance of the <br/>organization and the degree of maturity of the 'management system'. It also <br/>helps to identify areas for improvement in the organization, to determine <br/>priorities, and to set a baseline for further improvement.<br/>'Senior management' means the person who, or group of people which, directs, <br/>controls and assesses an organization at the highest level.<br/>The term <i><b>management self-assessment</b></i> is also used, notably in the IAEA’s <br/>'safety standards' on 'quality assurance' in nuclear power plants.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id550skos:definition "See 'area: controlled area'.<br/>
See 'area: controlled area'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id551skos:definition "The total harm that would eventually be experienced by an exposed <br/>
group and its descendants as a result of the group’s 'exposure' to 'radiation' from <br/>a 'source'. (From Ref. [1].)<br/>
In its Publication 60 [16], the International Commission on Radiological <br/>Protection defines a measure of 'radiation detriment' that has the dimensions of <br/>probability and that could therefore also be considered a measure of 'risk'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id552skos:definition "See 'emergency:' 'nuclear or radiological emergency'.<br/>
See 'emergency:' 'nuclear or radiological emergency'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id553skos:definition "[The corresponding 'dose rate' expressed in millisieverts per hour.] (From <br/>
Ref. [2].)<br/>
<b>!</b> This usage is specific to the Transport Regulations, and should otherwise be <br/>
avoided.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id554skos:definition "See 'protection' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id555skos:definition "A person technically competent in 'radiation protection' matters relevant <br/>
for a given type of 'practice' who is designated by the 'registrant' or 'licensee' to <br/>oversee the application of relevant 'requirements' established in international <br/>'safety standards'. <br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id556skos:definition "Systematic arrangements which are aimed at providing adequate <br/>
consideration of 'radiation protection' measures. (From Ref. [2].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id557skos:definition "— Detrimental 'health effects' of 'exposure' to' radiation '(including the <br/>
likelihood of such effects occurring).<br/>
— Any other 'safety' related 'risks' (including those to ecosystems in the <br/>
environment) that might arise as a direct consequence of:<br/>
• 'Exposure' to 'radiation';<br/>• The presence of 'radioactive material' (including 'radioactive waste') or <br/>
its release to the environment;<br/>
• A loss of 'control' over a nuclear reactor core, nuclear chain reaction, <br/>
'radioactive source' or any other 'source' of 'radiation'. (From Ref. [22].)<br/>For the purposes of the IAEA 'safety standards', it is assumed that there is no <br/>threshold level of 'radiation' 'dose' below which there are no associated <br/>'radiation risks'. Safety Requirements and Safety Guides specify the <i>radiation<br/>exposures</i> and other 'risks' to which they refer.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id558skos:definition "See 'source' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id559skos:definition "A person trained in 'radiation protection' and other areas of specialization <br/>
necessary in order to be able to assess radiological conditions, to mitigate <br/>radiological consequences or to control 'doses' to responders.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id56skos:definition "An 'operation' undertaken by a State or group of States to which assistance <br/>
is provided by or through the IAEA in the form of materials, services, <br/>equipment, 'facilities' or information pursuant to an agreement between the <br/>IAEA and that State or group of States.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id560skos:definition "A number by which the 'absorbed dose' in a tissue or organ is multiplied to <br/>
reflect the 'relative biological effectiveness' of the 'radiation' in inducing <i>stochastic <br/>effects</i> at low 'doses', the result being the 'equivalent dose'.<br/>
Values are selected by the International Commission on Radiological <br/>Protection to be representative of the relevant <i>relative biological effectiveness<br/></i>and are broadly compatible with the values previously recommended for <br/>'quality factors' in the definition of 'dose equivalent'. The <i>radiation weighting <br/>factor</i> values recommended by the International Commission on Radiological <br/>Protection [16] are:<br/>
Type of 'radiation'<br/>
'w'R <br/>
Photons, all energies<br/>
1<br/>
Electrons and muons, all energiesa<br/>
1<br/>
Neutrons, energy:<br/>
<10 keV<br/>
5<br/>
10 keV to 100 keV<br/>
>100 keV to 2 MeV<br/>
>2 MeV to 20 MeV<br/>
>20 MeV<br/>
5<br/>
Protons, other than recoil protons, energy >2 MeV<br/>
5<br/>
Alpha particles, 'fission fragments', heavy nuclei<br/>
a<br/>
Excluding Auger electrons emitted from radionuclides <br/>bound to DNA, for which special microdosimetric <br/>considerations apply.<br/>
If calculation of the 'radiation weighting factor' for neutrons requires a <br/>continuous function, the following approximation can be used, where 'E' is the <br/>neutron energy in MeV:<br/>
2<br/>
'w'<br/>
(ln( 'E'<br/>
e<br/>
)) /<br/>
= +<br/>
-<br/>
5 17<br/>
2<br/>
6<br/>
R<br/>
For 'radiation' types and energies not included in the table, 'w ' can be taken to <br/>
R<br/>
'—'<br/>
be equal to 'Q 'at 10 mm depth in the 'ICRU sphere' and can be obtained as <br/>follows:<br/>
•<br/>
1<br/>
'Q '=<br/>
'Q'('L')'D 'd'L'<br/>
Ú<br/>
'D'<br/>
'L'<br/>
0<br/>
where 'D' is the 'absorbed dose', 'Q'('L') is the 'quality factor' in terms of the <br/>'unrestricted linear energy transfer' 'L' in water, specified in Ref. [16], and 'D ' is <br/>
'L'<br/>
the distribution of 'D' in 'L'.<br/>
Ï<br/>
1<br/>
for<br/>
'L '£ 10<br/>
Ô<br/>
'Q'('L') = Ì .<br/>
0 32'L '- .<br/>
2 2<br/>
for<br/>
10 < 'L '< 100<br/>
Ô 300/ 'L 'for<br/>
'L'<br/>
Ó<br/>
≥ 100<br/>
where 'L' is expressed in keV/mm.<br/>
<b>radioactive</b>' (adjective)'<br/>
1. Exhibiting 'radioactivity'; emitting or relating to the emission of <br/>
'ionizing radiation' or particles.<br/>
This is the ‘scientific’ definition, and should not be confused with the <br/>‘regulatory’ definition (2).<br/>
2. Designated in national law or by a 'regulatory body' as being subject to <br/>
'regulatory control' because of its 'radioactivity'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id561skos:definition "The 'radioactive material' together with any contaminated or activated <br/>
solids, liquids and gases within the 'packaging'. (From Ref. [2].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id562skos:definition "See 'discharge' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id563skos:definition "See 'equilibrium, radioactive'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id564skos:definition "See 'half-life' (2).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id565skos:definition "1. Material designated in national law or by a 'regulatory body' as being <br/>
subject to 'regulatory control' because of its 'radioactivity'.<br/>
<b>!</b> 'Radioactive material' should be used in the singular unless reference is <br/>
expressly being made to the presence of various types of 'radioactive material'.<br/>Some States use the term <i><b>radioactive substance</b></i> for this regulatory purpose. <br/>However, the term 'radioactive substance' is also sometimes used to indicate <br/>that the scientific use of 'radioactive' (see 'radioactive' (1)) is intended, rather <br/>than the regulatory meaning of 'radioactive' (see 'radioactive' (2)) suggested by <br/>the term 'radioactive' 'material'. It is therefore essential that any such <br/>distinctions in meaning are clarified.<br/>In regulatory terminology in some States, 'radioactive material' ceases to be <br/>'radioactive material' when it becomes 'radioactive waste'; the term <i>radioactive <br/>substance</i> is used to cover both, i.e. 'radioactive substance' includes <i>radioactive <br/>material</i> and 'radioactive waste'.<br/>
2. Any material containing radionuclides where both the 'activity '<br/>
'concentration' and the total 'activity' in the 'consignment' exceed the values <br/>specified in paras 401–406 [of the Transport Regulations]. (From Ref. [2].)<br/>
<b>!</b> This usage is specific to the Transport Regulations, and should otherwise be <br/>
avoided.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id566skos:definition "See 'source' (2).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id567skos:definition "See 'safety of radioactive sources'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id568skos:definition "See 'security of radioactive sources'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id569skos:definition "See 'radioactive material' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id57skos:definition "See 'dispersion'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id570skos:definition "See 'waste, radioactive'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id571skos:definition "See 'waste management, radioactive'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id572skos:definition "See 'waste management facility, radioactive'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id573skos:definition "The phenomenon whereby atoms undergo spontaneous random <br/>
disintegration, usually accompanied by the emission of 'radiation'.<br/>
<b>!</b> In <br/>
'IAEA publications', 'radioactivity' should be used only to refer to the <br/>
phenomenon. To refer to the physical quantity or to an amount of a <br/>'radioactive substance', use 'activity'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id574skos:definition "A person who in the event of a 'nuclear or radiological emergency' assists <br/>
the 'operator' of a 'dangerous source' by performing 'radiation' 'surveys', performing <br/>'dose' 'assessments', controlling 'contamination', ensuring the <i>radiation protection<br/></i>of 'emergency workers' and formulating recommendations on 'protective actions'.<br/>
The radiological assessor would generally be the 'radiation protection officer'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id575skos:definition "See 'emergency'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id576skos:definition "See 'nuclear material' and 'radioactive material'.<br/>
See 'nuclear material' and 'radioactive material'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id577skos:definition "See 'protection' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id578skos:definition "See 'survey'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id579skos:definition "See 'sabotage'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id58skos:definition "The reduction in intensity of 'radiation' passing through matter due to <br/>
'processes' such as 'absorption' and scattering.<br/>
By analogy, also used in other situations in which some radiological property, <br/>characteristic or parameter is gradually reduced in the course of passing <br/>through a medium (e.g. the reduction in 'activity concentration' in groundwater <br/>passing through the 'geosphere' due to 'processes' such as' sorption').<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id580skos:definition "See 'terrorism'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id581skos:definition "See 'terrorism'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id582skos:definition "<b>!</b> ‘Radionuclear’ is not a legitimate word. See 'nuclear material' and 'radioactive '<br/>
'material'.<br/>'Radionuclear' has been used in nuclear medicine to mean ‘involving the use of <br/>radionuclides’; thus ‘'radionuclear' tests’ in nuclear medicine has been used to <br/>mean tests in which radiopharmaceuticals are administered. This usage <br/>should be avoided.<br/>'Radionuclear' has also been used as a journalese shorthand form for ‘nuclear <br/>and/or radiological’, as in the terms ‘'radionuclear' weapon’ and ‘<i>radionuclear <br/>emergency</i>’, or for ‘nuclear and/or 'radioactive'’, as in the term ‘<i>radionuclear<br/></i>material’. These and other such usages should be avoided.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id583skos:definition "Radionuclides that occur naturally on Earth in significant quantities.<br/>
The term is usually used to refer to the primordial radionuclides potassium-<br/>40, uranium-235, uranium-238, thorium-232 and their 'radioactive' decay <br/>products.<br/>Contrasted with radionuclides of artificial origin, and also with artificial <br/>radionuclides, anthropogenic radionuclides and human-made radionuclides.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id584skos:definition "1. Any combination of isotopes of the element 'radon'.<br/>
2. Radon-222.<br/>
When contrasted with 'thoron' (radon-220).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id585skos:definition "The short lived 'radioactive' decay products of radon-222.<br/>
This includes the decay chain up to but not including lead-210, namely <br/>polonium-218 (sometimes called radium <br/>
A), lead-214 (radium <br/>
B), <br/>
bismuth-214 (radium C) and polonium-214 (radium C′), plus traces of <br/>astatine-218, thallium-210 (radium C″) and lead-209. Lead-210 (radium D), <br/>which has a 'half-life' of 22.3 years, and its 'radioactive' progeny — bismuth-210 <br/>(radium E) and polonium-210 (radium F), plus traces of mercury-206 and <br/>thallium-206 — are, strictly, progeny of radon-222, but they are not normally <br/>included in the meaning of the term 'radon progeny', because they will not <br/>normally be present in significant amounts in airborne form. The stable decay <br/>product lead-206 is sometimes known as radium G.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id586skos:definition "For a nuclear chain reacting medium:<br/>
'r '=<br/>
1<br/>
1 - 'K'eff<br/>
where 'K ' is the ratio between the number of fissions in two succeeding <br/>
eff<br/>
generations (later to earlier) of the chain reaction.<br/>
A measure of the 'deviation' from 'criticality' of a nuclear chain reacting <br/>medium, such that positive values correspond to a supercritical state and <br/>negative values correspond to a subcritical state.<br/>
<i><b>shutdown reactivity.</b></i> The 'reactivity' when all 'control' devices are <br/>introducing their maximum negative 'reactivity'.<br/>
A reactor is shut down quickly by moving 'control' devices rapidly into position <br/>to introduce their negative 'reactivity' into the core.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id587skos:definition "See 'level'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id588skos:definition "Provision of alternative (identical or diverse) 'structures, systems and '<br/>
'components', so that any one can perform the required function regardless of <br/>the state of 'operation' or 'failure' of any other.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id589skos:definition "See 'kerma'.<br/>
See 'kerma'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id59skos:definition "See 'risk' (3).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id590skos:definition "An idealized human with characteristics defined by the International <br/>
Commission on Radiological Protection for 'radiation protection 'purposes.<br/>
Reference values for eight 'reference individuals' — a newborn; a one year old; <br/>a five year old; a ten year old; male and female 15 year olds; and male and <br/>female adults — are given in Ref. [36]. These reference values are based on <br/>data for western European and North American populations, but Ref. [36] <br/>also provides additional information on individual variation among grossly <br/>normal individuals resulting from differences in age, gender, race and other <br/>factors.<br/>This is a refinement of the 'Reference Man' concept.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id591skos:definition "See 'level'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id592skos:definition "An idealized adult Caucasian human male defined by the International <br/>
Commission on Radiological Protection for the purpose of <i>radiation protection <br/>assessment</i>. (From Ref. [1].)<br/>
See Ref. [37]. Although this is now being superseded by the more general <br/>concept of the 'reference individual' (see Ref. [36]), some concepts and <br/>quantities are still defined in terms of 'Reference Man'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id593skos:definition "See 'registration'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id594skos:definition "A form of 'authorization' for 'practices' of low or moderate 'risks' whereby <br/>
the 'legal person' responsible [i.e. <i><b>responsible legal person</b></i>] for the 'practice' has, <br/>as appropriate, prepared and submitted a 'safety assessment' of the 'facilities' and <br/>equipment to the 'regulatory body'. The 'practice' or use is authorized with <br/>conditions or limitations as appropriate. The requirements for <i>safety assessment<br/></i>and the conditions or limitations applied to the 'practice' should be less severe <br/>than those for licensing. (From Ref. [1].)<br/>
Typical 'practices' that are amenable to 'registration' are those for which: <br/>(a) 'safety' can largely be ensured by the 'design' of the 'facilities' and equipment; <br/>(b) the operating 'procedure's are simple to follow; (c) the 'safety' training <br/>
requirements are minimal; and (d) there is a history of few problems with <br/>'safety' in 'operations'. 'Registration' is best suited to those 'practices' for which <br/>'operations' do not vary significantly.<br/>The holder of a current 'registration' is termed a <i><b>registrant</b></i>. Other derivative <br/>terms should not be needed; a 'registration' is a product of the <i>authorization<br/>process</i>, and a 'practice' with a current 'registration' is an authorized' practice'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id595skos:definition "An authority or authorities designated or otherwise recognized by a <br/>
government for regulatory purposes in connection with 'protection and safety'. <br/>(From Ref. [1].)<br/>
<b>!</b> Superseded by the term 'regulatory body', which should generally be used. The <br/>
term 'Regulatory Authority' (with initial capitals) has been retained in <br/>publications where consistency with the BSS was necessary.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id596skos:definition "1. An authority or a system of authorities designated by the government <br/>
of a State as having legal authority for conducting the regulatory 'process', <br/>including issuing 'authorizations', and thereby regulating 'nuclear', 'radiation', <br/>'radioactive waste' and 'transport' 'safety'.<br/>
The national 'competent authority' for the regulation of <i>radioactive material<br/>transport safety</i> (see Ref. [2]) is included in this description, as is the <br/>'Regulatory Authority' for 'radiation protection and safety' (see Ref. [1]).<br/>
<b>!</b> Supersedes <br/>
the <br/>
term <br/>
'Regulatory Authority' as used in the BSS. The term <br/>
'Regulatory Authority' (with initial capitals) has been retained in publications <br/>where consistency with the BSS was necessary.<br/>
2. [For each Contracting Party any body or bodies given the legal <br/>
authority by that Contracting Party to grant 'licences' and to regulate the 'siting', <br/>'design', 'construction', 'commissioning', 'operation' or 'decommissioning' of <i>nuclear <br/>installations</i>.] (From Ref. [4].)<br/>
3. [Any body or bodies given the legal authority by the Contracting Party <br/>
to regulate any aspect of the 'safety' of 'spent fuel' or <i>radioactive waste <br/>management</i> including the granting of 'licences'.] (From Ref. [5].)<br/>
4. [An entity or organization or a system of entities or organizations <br/>
designated by the government of a State as having legal authority for exercising <br/>'regulatory control' with respect to 'radioactive sources', including issuing <br/>
'authorizations', and thereby regulating one or more aspects of the 'safety' or <br/>'security of' 'radioactive sources'.] (From Ref. [11].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id597skos:definition "See 'control' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id598skos:definition "See 'inspection'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id599skos:definition "See 'remediation'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id6skos:definition "1. See 'sorption'.<br/>
2. See 'lung absorption type'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id60skos:definition "See 'assessment '(2):' independent assessment'.<br/>
See 'assessment '(2):' independent assessment'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id600skos:definition "A relative measure of the effectiveness of different 'radiation' types at <br/>
inducing a specified 'health effect', expressed as the inverse ratio of the <i>absorbed <br/>doses</i> of two different 'radiation' types that would produce the same degree of a <br/>defined biological 'end point'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id601skos:definition "[The ratio of the 'dose coefficient' calculated using specific information for <br/>
one or more parameter values, to the corresponding 'dose coefficient' given in an <br/>International Commission on Radiological Protection report calculated using <br/>reference values for all parameters.] (From Ref. [21].)<br/>
<b>!</b> This is not a 'dose', and therefore the term is misleading.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id602skos:definition "See 'risk' (3).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id603skos:definition "The probability that a 'system' or 'component' will meet its minimum <br/>
performance requirements when called upon to do so.<br/>
See also 'availability'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id604skos:definition "See 'maintenance'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id605skos:definition "The non-urgent removal or extended exclusion of people from a <br/>
contaminated area to avoid 'chronic exposure'.<br/>
'Relocation' is a 'longer term protective action'. It may be a continuation of the <br/>'urgent protective action' of 'evacuation'.<br/>'Relocation' is considered to be <i><b>permanent relocation</b></i> (sometimes termed <br/><b>['resettlement'</b><b>]</b>) if it continues for more than a year or two and return is not <br/>foreseeable; otherwise it is <i><b>temporary relocation</b></i>.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id606skos:definition "Unit of 'dose equivalent' and 'effective dose equivalent', equal to 0.01 Sv.<br/>
Superseded by the 'sievert (Sv)'.<br/>Abbreviation of 'röntgen' equivalent man.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id607skos:definition "Action taken when a specified 'action level' is exceeded, to reduce <br/>
'radiation' 'doses' that might otherwise be received, in an 'intervention' situation <br/>involving 'chronic exposure'. (From Ref. [1].)<br/>
'Remedial actions' could also be termed 'longer term protective actions', but <br/>'longer term protective actions' are not necessarily 'remedial actions'.<br/>See also 'protective action' and 'root cause'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id608skos:definition "Any measures that may be carried out to reduce the 'radiation' 'exposure'<br/>
from existing 'contamination' of land areas through actions applied to the <br/>'contamination' itself (the 'source') or to the 'exposure pathways' to humans.<br/>
Complete removal of the 'contamination' is not implied.<br/>The more informal term 'cleanup' is also used. If used, it should be used with <br/>the same meaning as 'remediation', not to attempt to convey a different <br/>meaning.<br/>The terms 'rehabilitation 'and' restoration' may be taken to imply that the <br/>conditions that prevailed before the 'contamination' can be achieved again, <br/>which is not normally the case (e.g. owing to the effects of the <i>remedial action<br/></i>itself). Their use is discouraged.<br/>See 'decontamination'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id609skos:definition "See 'cause': 'root cause'.<br/>
See 'cause': 'root cause'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id61skos:definition "The granting by a 'regulatory body' or other governmental body of written <br/>
permission for an 'operator' to perform specified 'activities'.<br/>
'Authorization' could include, for example, licensing, certification or <br/>'registration'.<br/>The term 'authorization' is also sometimes used to describe the document <br/>granting such permission.<br/>'Authorization' is normally a more formal 'process' than 'approval'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id610skos:definition "Action on a non-conforming product to make it acceptable for its <br/>
intended use (ISO 9000). See also 'cause':' direct cause'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id611skos:definition "A 'nuclear facility' where 'waste' is emplaced for 'disposal'.<br/>
<i><b>geological repository.</b></i> A 'facility' for 'radioactive waste disposal' located <br/>underground (usually several hundred metres or more below the surface) <br/>in a stable geological formation to provide long term isolation of <br/>radionuclides from the 'biosphere'.<br/>
<i><b>near surface repository.</b></i> A 'facility' for 'radioactive waste disposal' located at <br/>or within a few tens of metres of the Earth’s surface.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id612skos:definition "A 'process' or 'operation', the purpose of which is to extract 'radioactive'<br/>
isotopes from 'spent fuel' for further use.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id613skos:definition "'Required' by (national or international) law or regulations, or by IAEA <br/>
Safety Fundamentals' 'or Safety Requirements.<br/>
<b>!</b> In <br/>
'IAEA publications', 'required' (and other terms such as 'requirement' derived <br/>
from the verb ‘require’) should be used in this sense only. Care should be <br/>taken to avoid confusion. The more general sense of something that is <br/>necessary should be expressed using other words.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id614skos:definition "[A nuclear reactor used mainly for the generation and utilization of <br/>
neutron flux and 'ionizing radiation' for research and other purposes, including <br/>experimental 'facilities' associated with the reactor and 'storage', handling and <br/>'treatment' 'facilities' for 'radioactive materials' on the same site that are directly <br/>
related to safe 'operation' of the 'research reactor'. 'Facilities' commonly known as <br/>'critical' assemblies are included.]<br/>
<b>!</b> This definition is particular to the Code of Conduct on the Safety of Research <br/>
Reactors [38].<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id615skos:definition "See 'relocation'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id616skos:definition "See 'dose concepts'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id617skos:definition "The sum of the heat originating from 'radioactive' decay and shutdown <br/>
fission and the heat stored in reactor related 'structures' and in heat <i>transport<br/></i>media.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id618skos:definition "An organization designated or otherwise recognized by a State as being <br/>
responsible for managing or implementing any aspect of an <i>emergency <br/>response</i>. <br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id619skos:definition "The period of time necessary for a 'component' to achieve a specified <br/>
output state from the time that it receives a signal requiring it to assume that <br/>output state.<br/>
<b>!</b> Note that this is not related to 'emergency response'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id62skos:definition "See 'facilities and activities'.<br/>
See 'facilities and activities'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id620skos:definition "See 'licence 'and' registration'.<br/>
See 'licence 'and' registration'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id621skos:definition "See 'remediation'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id622skos:definition "See 'linear energy transfer (LET)'.<br/>
See 'linear energy transfer (LET)'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id623skos:definition "See 'use'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id624skos:definition "Depending on the context, the term 'risk' may be used to represent a <br/>quantitative measure (as, for example, in definitions (1) and (2)) or as a <br/>qualitative concept (as often for definition (3)).<br/>
1. A multiattribute quantity expressing hazard, danger or chance of <br/>
harmful or injurious consequences associated with actual or <i>potential <br/>exposures</i>. It relates to quantities such as the probability that specific <br/>deleterious consequences may arise and the magnitude and character of such <br/>consequences. (From Ref. [1].)<br/>
In mathematical terms, this can be expressed generally as a set of triplets, 'R' = <br/>
{〈'S '⏐'p '⏐'X '〉}, where 'S ' is an identification or description of a 'scenario' i, 'p ' is <br/>
i<br/>
i<br/>
i<br/>
i<br/>
i<br/>
the probability of that 'scenario' and 'X ' is a measure of the consequence of the <br/>
i<br/>
'scenario'. The concept of 'risk' is sometimes also considered to include <br/>uncertainty in the probabilities 'p ' of the 'scenarios'.<br/>
i<br/>
2. The mathematical mean (expectation value) of an appropriate <br/>
measure of a specified (usually unwelcome) consequence:<br/>
'R '=<br/>
'p C'<br/>
 i i<br/>
i<br/>
where 'p ' is the probability of occurrence of 'scenario' or 'event sequence' i and 'C'<br/>
i<br/>
i<br/>
is a measure of the consequence of that 'scenario' or 'event sequence'.<br/>
Typical consequence measures 'C ' include core damage frequency, the <br/>
i<br/>
estimated number or probability of 'health effects', etc.<br/>If the number of 'scenarios' or 'event sequences' is large, the summation is <br/>replaced by an integral.<br/>The summing of 'risks' associated with 'scenarios' or 'event sequences' with widely <br/>differing values of 'C ' is controversial. In such cases the use of the term <br/>
i<br/>
‘expectation value’, although mathematically correct, is misleading and <br/>should be avoided if possible.<br/>
Methods for treating uncertainty in the values of 'p ' and 'C ', and in particular <br/>
i<br/>
i<br/>
whether such uncertainty is represented as an element of 'risk' itself or as <br/>uncertainty in estimates of 'risk', vary.<br/>
3. The probability of a specified 'health effect' occurring in a person or <br/>
group as a result of 'exposure' to 'radiation'.<br/>
The 'health effect(s)' in question must be stated — e.g. 'risk' of fatal cancer, <i>risk<br/></i>of serious 'hereditary effects' or overall 'radiation detriment' — as there is no <br/>generally accepted ‘default’.<br/>Commonly expressed as the product of the probability that 'exposure' will <br/>occur and the probability that the 'exposure', assuming that it occurs, will cause <br/>the specified 'health effect'. The latter probability is sometimes termed the <br/><i><b>conditional risk</b></i>.<br/>
<i><b>annual risk.</b></i> The probability that a specified 'health effect' will occur at <br/>some time in the future in an individual as a result of 'radiation' <i>exposure<br/></i>incurred or committed in a given year, taking account of the probability <br/>of 'exposure' occurring in that year.<br/>
<b>!</b> This is not the probability of the 'health effect' occurring in the year in question; <br/>
it is the 'lifetime risk' resulting from the 'annual dose' for that year.<br/>
<i><b>attributable risk.</b></i> The 'risk' of a specified 'health effect' assumed to result <br/>from a specified 'exposure'.<br/>
<i><b>excess relative risk.</b></i> The ratio of the 'excess risk' of a specified <i>stochastic <br/>effect</i> to the probability of the same effect in the unexposed population, <br/>i.e. the 'relative risk' minus one. In theory, this should be equal to the <br/>'attributable risk' from the 'exposure' received by the exposed group, but <br/>'excess relative risk' is normally used in the context of observed numbers of <br/>effects, whereas 'attributable risk' normally refers to a figure calculated on <br/>the basis of a known or estimated 'exposure'.<br/>
<i><b>excess risk.</b></i> The difference between the incidence of a specified <i>stochastic <br/>effect</i> observed in an exposed group to that in an unexposed <i>control<br/></i>group.<br/>
<i><b>lifetime risk.</b></i> The probability that a specified 'health effect' will occur at <br/>some time in the future in an individual as a result of 'radiation' 'exposure'.<br/>
<i><b>relative risk.</b></i> The ratio between the incidence of a specified <i>stochastic <br/>effect</i> observed in an exposed group and that in an unexposed <i>control<br/></i>group. (See 'control' (2).)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id625skos:definition "See 'assessment' (1).<br/>
<b>risk coefficient, </b>'g'<br/>
The 'lifetime risk' or 'radiation detriment' assumed to result from 'exposure' to <br/>
unit 'equivalent dose' or 'effective dose'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id626skos:definition "Sometimes used as a synonym for 'risk coefficient'. However, this is different <br/>from the normal medical use of the term 'risk factor' to indicate a factor that <br/>influences an individual’s 'risk', and therefore should be avoided.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id627skos:definition "A plant specific real time 'analysis' tool used to determine the <br/>
instantaneous 'risk' based on the actual status of the 'systems' and 'components'. At <br/>any given time, the 'risk monitor' reflects the current plant configuration in <br/>terms of the known status of the various 'systems' and/or 'components', e.g. <br/>whether there are any 'components' out of service for 'maintenance' or tests. The <br/>'model' used by the 'risk monitor' is based on, and is consistent with, the <i>living <br/>probabilistic safety assessment </i>for the 'facility'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id628skos:definition "A 'conceptual model' for estimating the 'risk' from 'radiation exposure' at low <br/>
'doses' and 'dose rates' on the basis of epidemiological evidence concerning the <br/>'risk' from high 'doses' and/or 'dose rates'.<br/>
<i><b>additive risk projection model.</b></i> A 'risk projection model' in which <br/>'exposure' is assumed to lead to an 'attributable risk' that is proportional to <br/>the 'dose' but independent of the natural probability of the effect.<br/>
<i><b>multiplicative risk projection model.</b></i> A 'risk projection model' in which <br/>'exposure' is assumed to lead to an 'attributable risk' that is proportional to <br/>the 'dose' and to the natural probability of the effect.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id629skos:definition "Unit of 'exposure', equal to 2.58 × 10–4 C/kg (exactly).<br/>
Superseded by the SI unit C/kg.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id63skos:definition "See 'discharge' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id630skos:definition "See 'cause'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id631skos:definition "See 'uptake' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id632skos:definition "See 'monitoring' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id633skos:definition "[Any deliberate act directed against a 'nuclear facility' or 'nuclear material'<br/>
in use, 'storage' or 'transport' which could directly or indirectly endanger the <br/>health and 'safety' of personnel, the public or the environment by 'exposure' to <br/>'radiation' or release of 'radioactive substances'.]<br/>
From and particular to the Revised Convention on the Physical Protection of <br/>Nuclear Material and Nuclear Facilities [30]. <br/>See: http://www.iaea.org/NewsCenter/Features/PhysicalProtection/index.html<br/>Use this word with caution and avoid such journalese terms as <i>nuclear <br/>sabotage</i>, 'radiological sabotage'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id634skos:definition "An agreement between the IAEA and one or more Member States which <br/>
contains an undertaking by one or more of those States not to use certain items <br/>in such a way as to further any military purpose and which gives the IAEA the <br/>right to observe compliance with such undertaking. Such an agreement may <br/>concern:<br/>
(a)<br/>
An IAEA project; <br/>
(b)<br/>
A bilateral or multilateral arrangement in the field of nuclear energy <br/>under which the IAEA may be asked to administer safeguards; or<br/>
(c)<br/>
Any of a State’s nuclear 'activities' unilaterally submitted to IAEA <br/>safeguards.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id635skos:definition "See 'nuclear safety' and 'protection and safety'.<br/>
See 'nuclear safety' and 'protection and safety'.<br/>
In the Fundamental Safety Principles (Safety Fundamentals), the generalized <br/>usage in this particular text of the term 'safety' (i.e. to mean <i>protection and <br/>safety</i>) is explained as follows (Ref. [22], paras 3.1 and 3.2):<br/>
“3.1. For the purposes of this publication, ‘'safety'’ means the 'protection' of <br/>people and the environment against 'radiation risks', and the 'safety' of <br/>'facilities and activities' that give rise to 'radiation risks'. ‘'Safety'’ as used here <br/>and in the IAEA 'safety standards' includes the 'safety' of <i>nuclear <br/>installations</i>, radiation 'safety', the 'safety' of <i>radioactive waste management<br/></i>and 'safety' in the 'transport' of 'radioactive material'; it does not include <br/>non-radiation-related aspects of 'safety'.<br/>
3.2. “'Safety' is concerned with both 'radiation risks' under normal <br/>circumstances and 'radiation risks' as a consequence of 'incidents'4, as well as <br/>with other possible direct consequences of a loss of control over a nuclear <br/>reactor core, nuclear chain reaction, 'radioactive source' or any other <br/>'source' of radiation. 'Safety measures' include actions to prevent <i>incidents<br/></i>and arrangements put in place to mitigate their consequences if they were <br/>to occur.” <br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id636skos:definition "A single action taken by a 'safety actuation system'.<br/>
For example, insertion of a 'control' rod, closing of 'containment' valves or <br/>'operation' of the 'safety' injection pumps.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id637skos:definition "See 'plant equipment'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id638skos:definition "See 'analysis'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id639skos:definition "See 'assessment' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id64skos:definition "See 'facilities and activities'.<br/>
See 'facilities and activities'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id640skos:definition "A collection of arguments and evidence in support of the 'safety' of a <br/>
'facility or activity'.<br/>
This will normally include the findings of a 'safety assessment' and a statement <br/>of confidence in these findings.<br/>For a 'repository', the 'safety case' may relate to a given stage of development. In <br/>such cases, the 'safety case' should acknowledge the existence of any <br/>unresolved issues and should provide guidance for work to resolve these <br/>issues in future development stages.<br/>
“4 ‘'Incidents'’ includes 'initiating events', 'accident precursors', 'near misses', 'accidents'<br/>
and unauthorized acts (including 'malicious' and non-malicious acts).”<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id641skos:definition "A group of experts from the 'operating organization' convened to advise <br/>
on the 'safety' of 'operation' of an 'authorized facility'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id642skos:definition "The assembly of characteristics and attitudes in organizations and <br/>
individuals which establishes that, as an overriding priority, <i>protection and <br/>safety</i> 'issues' receive the attention warranted by their significance.<br/>
For a more detailed discussion, see Ref. [39].<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id643skos:definition "A specific purpose that must be accomplished for 'safety'.<br/>
Reference [40] lists 19 'safety functions' to be fulfilled by the 'design' of a nuclear <br/>power plant in order to meet three general 'safety requirements':<br/>
(a) The capability to safely shut down the reactor and maintain it in a safe <br/>
shutdown condition during and after appropriate 'operational states' and <br/>'accident conditions';<br/>
(b) The capability to remove 'residual heat' from the reactor core after <br/>
shutdown, and during and after appropriate 'operational states' and <br/>'accident conditions'; <br/>
(c) The capability to reduce the potential for the release of 'radioactive '<br/>
'material' and to ensure that any releases are within 'prescribed limits' during <br/>and after 'operational states' and within 'acceptable limits' during and after <br/>'design basis accidents'.<br/>
This guidance is commonly condensed into a succinct expression of three <br/><i><b>main safety functions</b></i> for nuclear power plants:<br/>
(a) 'Control' of 'reactivity';<br/>(b) Cooling of 'radioactive material'; <br/>(c) 'Confinement' of 'radioactive material'.<br/>
In earlier 'IAEA publications', ‘basic 'safety function'’ and ‘fundamental <br/>
'safety function'’ were also used.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id644skos:definition "The assembly of equipment designated to perform all actions required for <br/>
a particular 'postulated initiating event' to ensure that the 'limits' specified in the <br/>
'design basis' for 'anticipated operational occurrences' and <i>design basis accidents<br/></i>are not exceeded.<br/>
<b>!</b> The term ‘group’ is also used (with various qualifying adjectives, e.g. <br/>
'maintenance' group, 'commissioning' group) in the more obvious sense of a <br/>group of people involved in a particular area of work. Such terms may need to <br/>be defined if there is any chance of confusion with 'safety group'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id645skos:definition "A quantity used in 'assessments' as a measure of the radiological impact of <br/>
a 'source' or 'practice', or of the performance of 'protection and safety' provisions, <br/>other than a prediction of 'dose' or 'risk'.<br/>
Such quantities are most commonly used in situations where predictions of <br/>'dose' or 'risk' are unlikely to be reliable, e.g. long term 'assessments' of <br/>'repositories'. They are normally either:<br/>
(a) Illustrative calculations of 'dose' or 'risk' quantities, used to give an <br/>
indication of the possible magnitude of 'doses' or 'risks' for comparison with <br/>criteria; or<br/>
(b) Other quantities, such as radionuclide concentrations or fluxes, that are <br/>
considered to give a more reliable indication of impact, and that can be <br/>compared with other relevant data.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id646skos:definition "'Deviations' from current 'safety standards' or 'practices', or weaknesses in <br/>
'facility' 'design' or 'practices' identified by plant 'events', with a potential impact on <br/>'safety' because of their impact on 'defence in depth', 'safety' margins or <i>safety <br/>culture</i>.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id647skos:definition "Passive 'systems', automatically or manually initiated 'safety systems', or <br/>
administrative 'controls 'that are provided to ensure that the 'required' <i>safety <br/>functions</i> are achieved.<br/>
Often expressed as:<br/>
(a) Hardware, i.e. passive and active 'safety systems';<br/>(b) Software, including personnel and 'procedures' as well as computer <br/>
software; <br/>
(c) Management 'control', particularly preventing 'defence in depth'<br/>
degradation (through 'quality assurance', 'preventive maintenance', <br/>'surveillance testing', etc.) and reacting appropriately to experience <br/>
feedback from degradations that do occur (e.g. determining <i>root causes<br/></i>and taking corrective actions).<br/>
See also 'defence in depth'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id648skos:definition "See 'limit'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id649skos:definition "Any action that might be taken, condition that might be applied or <br/>
'procedure' that might be followed to fulfil the basic 'requirements' of Safety <br/>Requirements (see footnote 2).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id65skos:definition "See 'limit'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id650skos:definition "[Measures intended to minimize the likelihood of 'accidents' involving <br/>
'radioactive sources' and, should such an 'accident' occur, to mitigate its <br/>consequences.] (From Ref. [11].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id651skos:definition "See 'plant equipment'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id652skos:definition "See 'plant equipment'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id653skos:definition "Standards of 'safety' issued pursuant to Article III(A)(6)10 of the Statute of <br/>
the IAEA [31].<br/>
'Safety standards' issued since 1997 in the IAEA Safety Standards Series are <br/>designated as Safety Fundamentals, Safety Requirements or Safety Guides. <br/>
10 [The Agency is authorized…] To establish or adopt, in consultation and, where <br/>
appropriate, in collaboration with the competent organs of the United Nations and with <br/>the specialized agencies concerned, standards of safety for protection of health and <br/>minimization of danger to life and property (including such standards for labour <br/>conditions)…”<br/>
Other 'IAEA publications', such as Safety Reports and TECDOCs (most of <br/>which are issued pursuant to Article VIII of the Statute), are not <i>safety <br/>standards</i>. Some 'safety standards' issued prior to 1997 in the IAEA Safety <br/>Series were designated Safety Standards, Codes, Regulations or Rules. <br/>Furthermore, some publications issued in the Safety Series were not <i>safety <br/>standards</i>, notably those designated Safety Practices or Procedures and Data.<br/>'Requirements', regulations, standards, rules, codes of practice or <br/>recommendations established to protect people and the environment against <br/>'ionizing radiation' and to minimize danger to life and property (see <br/>footnote 2).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id654skos:definition "See 'plant equipment'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id655skos:definition "The levels at which protective devices are automatically actuated in the <br/>
event of 'anticipated operational occurrences' or 'accident conditions', to prevent <br/>'safety limits' from being exceeded.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id656skos:definition "See 'plant equipment'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id657skos:definition "The sensing of one or more variables indicative of a specific 'postulated '<br/>
'initiating event', the signal processing, the initiation and completion of the <i>safety <br/>actions</i> 'required' to prevent the 'limits' specified in the 'design basis' from being <br/>exceeded, and the initiation and completion of certain services from the <i>safety <br/>system support features</i>.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id658skos:definition "A postulated or assumed set of conditions and/or 'events'.<br/>
Most commonly used in 'analysis' or 'assessment' to represent possible future <br/>conditions and/or 'events' to be modelled, such as possible 'accidents' at a <br/>'nuclear facility', or the possible future evolution of a 'repository' and its <br/>surroundings. A 'scenario' may represent the conditions at a single point in <br/>time or a single 'event', or a time history of conditions and/or 'events' (including <br/>'processes').<br/>See 'event'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id659skos:definition "A rapid 'emergency' shutdown of a nuclear reactor.<br/>
See 'anticipated transient without scram (ATWS)'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id66skos:definition "The release by the 'regulatory body' of an 'operator' (or a former 'operator') <br/>
from any further regulatory responsibilities in relation to an <i>authorized facility <br/></i>or' authorized activity'.<br/>
This may be a separate 'process' from termination of an 'authorization', e.g. <br/>termination of the responsibility to maintain active 'institutional control' over a <br/>'repository'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id660skos:definition "A type of 'analysis' aimed at eliminating from further consideration factors <br/>
that are less significant for 'protection' or 'safety' in order to concentrate on the <br/>more significant factors. This is typically achieved by consideration of very <br/>pessimistic hypothetical 'scenarios'.<br/>
'Screening' is usually conducted at an early stage in order to narrow the range <br/>of factors needing detailed consideration in an 'analysis' or 'assessment'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id661skos:definition "The distance from a 'facility' beyond which, for 'screening' purposes, <br/>
potential origins of a particular type of 'external event' can be ignored.<br/>
The definition in Ref. [41] had ‘'sources'’ instead of ‘origins’.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id662skos:definition "A value of the annual probability of occurrence of a particular type of <br/>
'event' below which, for 'screening' purposes, such an 'event' can be ignored.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id663skos:definition "See 'disposal' (3).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id664skos:definition "See 'source' (2).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id665skos:definition "See 'limit'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id666skos:definition "See ('nuclear')' security'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id667skos:definition "[Characteristics and attitudes in organizations and of individuals which <br/>
establish that 'security' issues receive the attention warranted by their <br/>significance.] (From Ref. [11].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id668skos:definition "[Measures to prevent unauthorized access or damage to, and loss, theft or <br/>
unauthorized transfer of, 'radioactive sources'.] (From Ref. [11].)<br/>
<b>!</b> This includes unauthorized access, theft and unauthorized transfer, <br/>
irrespective of the intent or state of knowledge of the perpetrator.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id669skos:definition "See 'waste management, radioactive' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id67skos:definition "The transfer of regulatory responsibility for specified 'radioactive material'<br/>
from one 'operator' to another.<br/>
<b>!</b> This does not necessarily involve any movement of the material itself.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id670skos:definition "See 'equipment qualification'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id671skos:definition "See 'assessment' (2).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id672skos:definition "See 'management system review'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id673skos:definition "See 'analysis'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id674skos:definition "See 'INES'.<br/>
See 'INES'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id675skos:definition "See 'INES'.<br/>
See 'INES'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id676skos:definition "Actual physical states or influences during the 'service life' of a 'structure, '<br/>
'system or component', including 'operating conditions' (normal and error <br/>induced), 'design basis' 'event' conditions and conditions following a <i>design basis<br/>event</i>.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id677skos:definition "See 'life'.<br/>
See 'life'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id678skos:definition "See 'plant states'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id679skos:definition "See 'plant states'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id68skos:definition "See 'use'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id680skos:definition "See 'health effects (of radiation): severe deterministic effect'.<br/>
See 'health effects (of radiation): severe deterministic effect'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id681skos:definition "The use of a 'structure' for 'protection' from an airborne plume and/or <br/>
deposited radionuclides.<br/>
An 'urgent protective action', used to provide shielding against <i>external <br/>exposure</i> and to reduce the 'intake' of airborne radionuclides by inhalation.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id682skos:definition "The specific movement of a 'consignment' from origin to destination. <br/>
(From Ref. [2].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id683skos:definition "See 'waste classes'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id684skos:definition "See 'reactivity'.<br/>
See 'reactivity'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id685skos:definition "The SI unit of 'equivalent dose' and 'effective dose', equal to 1 J/kg.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id686skos:definition "A release of 'radioactive material' to the environment that may result in <br/>
'doses' or levels of 'contamination' beyond national borders from the release <br/>which exceed international 'intervention levels' or 'action levels' for <i>protective <br/>actions</i>, including food restrictions and restrictions on commerce.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id687skos:definition "A 'failure' which results in the loss of capability of a 'system' or 'component'<br/>
to perform its intended 'safety function(s)', and any consequential <i>failure(s)<br/></i>which result from it.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id688skos:definition "A criterion (or requirement) applied to a 'system' such that it must be <br/>
capable of performing its task in the presence of any 'single failure'.<br/>
The <i><b>double contingency principle</b></i><b> </b>is a principle applied, for example, in the <br/>'design' of 'processes' for 'fuel' 'cycle' 'facilities', such that the 'design' for a <i>process<br/></i>must include sufficient 'safety' factors that a 'criticality accident' would not be <br/>possible unless at least two unlikely and independent changes in <i>process<br/></i>conditions were to occur concurrently.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id689skos:definition "See 'area'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id69skos:definition "The fraction of time for which a 'system' is capable of fulfilling its intended <br/>
purpose.<br/>
'Reliability' represents essentially the same information, but in a different <br/>form.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id690skos:definition "See 'emergency class'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id691skos:definition "See 'area:' 'site area'.<br/>
See 'area:' 'site area'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id692skos:definition "See 'characterization' (2).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id693skos:definition "The final stage of the 'siting' 'process' for a 'repository', based on detailed <br/>
investigations on the preferred site which provide site specific information <br/>needed for 'safety assessment'. This stage includes the finalization of the <br/>'repository design' and the preparation and submission of a 'licence' application to <br/>the 'regulatory body'.<br/>
'Site confirmation' follows 'site characterization'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id694skos:definition "'Analysis' of those factors at a site that could affect the 'safety' of a 'facility or '<br/>
'activity' on that site. This includes 'site' 'characterization', consideration of factors <br/>that could affect 'safety' features of the 'facility' or 'activity' so as to result in a <br/>release of 'radioactive material' and/or could affect the 'dispersion' of such <br/>material in the environment, as well as population and access issues relevant to <br/>'safety' (e.g. feasibility of 'evacuation', location of people and resources).<br/>
The 'analysis' for a site of the origins of 'external events' that could give rise to <br/>hazards with potential consequences for the 'safety' of a nuclear power plant <br/>constructed on that site. (The definition in Ref. [41] had ‘'sources'’ instead of <br/>‘origins’.)<br/>For a nuclear power plant, 'site evaluation' typically involves the following <br/>stages:<br/>
(a) 'Site selection' stage. One or more preferred candidate sites are selected <br/>
after the investigation of a large region, the rejection of unsuitable sites, <br/>and 'screening' and comparison of the remaining sites.<br/>
(b) 'Site' 'characterization' stage. This stage is further subdivided into:<br/>
• 'Site verification', in which the suitability of the site to host a nuclear <br/>
power plant is verified mainly according to predefined site <i>exclusion<br/></i>criteria;<br/>
• 'Site confirmation', in which the characteristics of the site necessary for <br/>
the purposes of 'analysis' and detailed 'design' are determined.<br/>
(c) Pre-operational stage. Studies and investigations begun in the previous <br/>
stages are continued after the start of 'construction' and before the start of <br/>'operation' of the plant, to complete and refine the 'assessment' of site <br/>
characteristics. The site data obtained allow a final 'assessment' of the <br/>simulation 'models' used in the final 'design'.<br/>
(d) Operational stage. Appropriate 'safety' related 'site evaluation' 'activities' are <br/>
carried out throughout the lifetime of the 'facility', mainly by means of <br/>'monitoring' and 'periodic safety review'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id695skos:definition "All persons working in the 'site area' of an 'authorized facility', either <br/>
permanently or temporarily.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id696skos:definition "See 'site evaluation'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id697skos:definition "The 'process' of selecting a suitable site for a 'facility', including appropriate <br/>
'assessment' and definition of the related 'design bases'.<br/>
The 'siting' 'process' for a 'nuclear installation' generally consists of site <i>survey<br/></i>and 'site selection'. Site 'survey' is the 'process' of identifying candidate sites for a <br/>'nuclear installation' after the investigation of a large region and the rejection <br/>of unsuitable sites. 'Site selection' is the 'process' of assessing the remaining sites <br/>by 'screening' and comparing them on the basis of 'safety' and other <br/>considerations to select one or more preferred candidate sites. See also <i>site <br/>evaluation</i>.<br/>The 'siting' 'process' for a 'repository' is particularly crucial to its long term 'safety'; <br/>it may therefore be a particularly extensive 'process', and is divided into the <br/>following stages:<br/>
— Concept and planning;<br/>— 'Area survey';<br/>— 'Site characterization'; <br/>— 'Site confirmation'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id698skos:definition "Levels of ground motion (representing the potential effects of <br/>
earthquakes) considered in the 'design basis' for a 'facility'.<br/>
'SL-1' corresponds to a less severe, more likely earthquake than 'SL-2'. In some <br/>States, 'SL-1' corresponds to a level with a probability of 10–2 per year of being <br/>exceeded, and 'SL-2' corresponds to a level with a probability of 10–4 per year <br/>of being exceeded.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id699skos:definition "See 'freight container'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id7skos:definition "See 'lung absorption type'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id70skos:definition "See 'dose concepts'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id700skos:definition "See 'health effects (of radiation)'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id701skos:definition "The interaction of an atom, molecule or particle with the solid surface at <br/>
a solid–solution or a solid–gas interface.<br/>
Used in the context of radionuclide 'migration' to describe the interaction of <br/>radionuclides in pore- or groundwater with soil or host rock, and of <br/>radionuclides in surface water bodies with suspended and bed sediments.<br/>A general term which includes <i><b>absorption</b></i> (interactions taking place largely <br/>within the pores of solids) and <i><b>adsorption</b></i> (interactions taking place on solid <br/>surfaces). The 'processes' involved can also be divided into <i><b>chemisorption<br/></b></i>(chemical bonding with the substrate) and <i><b>physisorption</b></i> (physical attraction, <br/>e.g. by weak electrostatic forces).<br/>In practice, 'sorption' may sometimes be difficult to distinguish from other <br/>factors affecting 'migration', such as filtration or 'dispersion'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id702skos:definition "1. Anything that may cause 'radiation' 'exposure' — such as by emitting <br/>
'ionizing radiation' or by releasing 'radioactive substances' or 'material' — and can <br/>be treated as a single entity for 'protection and safety' purposes.<br/>
For example, materials emitting 'radon' are 'sources' in the environment, a <br/>sterilization gamma irradiation unit is a 'source' for the 'practice' of <i>radiation<br/></i>preservation of food, an X ray unit may be a 'source' for the 'practice' of <br/>radiodiagnosis; a nuclear power plant is part of the 'practice' of generating <br/>electricity by nuclear fission, and may be regarded as a 'source' (e.g. with <br/>respect to 'discharges' to the environment) or as a collection of 'sources' (e.g. for <br/>occupational 'radiation protection' purposes). A complex or multiple <br/>installation situated at one location or site may, as appropriate, be considered <br/>a single 'source' for the purposes of application of international <i>safety <br/>standards</i>.<br/>
<i><b>natural source.</b></i> A naturally occurring 'source' of 'radiation', such as the sun <br/>and stars ('sources' of cosmic 'radiation') and rocks and soil (terrestrial <br/>'sources' of 'radiation').<br/>
Examples of 'natural sources' include <i>naturally occurring radioactive material <br/>(NORM)</i> associated with the processing of raw materials (i.e. feedstocks, <br/>intermediate products, final products, co-products and 'waste').<br/>
[<i><b>radiation source.</b></i> A 'radiation' generator, or a 'radioactive source' or other <br/>'radioactive material' outside the 'nuclear fuel cycles' of research and power <br/>reactors.] (Defined in the 2001 edition of the Code of Conduct on the <br/>Safety and Security of Radioactive Sources, but not included in the 2004 <br/>edition (see Ref. [11]).)<br/>
2.' Radioactive material' used as a 'source' of 'radiation'.<br/>
Such as those sources used for medical applications or in industrial <br/>instruments. These are, of course, 'sources' as defined in (1), but this usage is <br/>less general.<br/>
<i><b>dangerous source.</b></i> A 'source' that could, if not under 'control', give rise to <br/>'exposure' sufficient to cause 'severe deterministic effects'. This <br/>categorization is used for determining the need for <i>emergency response <br/>arrangements</i> and is not to be confused with categorizations of 'sources' for <br/>other purposes.<br/>
<i><b>disused source.</b></i> A 'radioactive source' that is no longer used, and is not <br/>intended to be used, for the 'practice' for which an 'authorization' has been <br/>granted. (From Ref. [11].)<br/>
The Joint Convention on the Safety of Spent Fuel Management and on the <br/>Safety of Radioactive Waste Management [5] refers to “disused <i>sealed <br/>sources</i>”, but does not define them. On the basis of this definition of <i>disused <br/>source</i> and the definition of 'sealed source' (see below), a disused <i>sealed source<br/></i>is a 'radioactive source' comprising 'radioactive material' that is permanently <br/>sealed in a capsule or closely bonded and in a solid form (excluding reactor <br/>'fuel elements') that is no longer used, and is not intended to be used, for the <br/>'practice' for which an 'authorization' has been granted.<br/>
<b>!</b> Note that a 'disused source' may still represent a significant radiological hazard. <br/>
It differs from a 'spent source' in that it may still be capable of performing its <br/>function; it may be disused because it is no longer needed.<br/>
<i><b>orphan source.</b></i> A 'radioactive source' which is not under <i>regulatory <br/>control</i>, either because it has never been under 'regulatory control' or <br/>because it has been abandoned, lost, misplaced, stolen or otherwise <br/>transferred without proper 'authorization'. (From Ref. [11].)<br/>
<i><b>radioactive source.</b></i> ['Radioactive material' that is permanently sealed in a <br/>capsule or closely bonded and in a solid form and which is not exempt <br/>from 'regulatory control'. This also includes any <i>radioactive material<br/></i>released if the 'radioactive source' is leaking or broken, but does not <br/>include material encapsulated for 'disposal', or 'nuclear material' within the <br/>'nuclear fuel cycles' of research and power reactors.] (From Ref. [11].)<br/>
This definition is particular to the Code of Conduct on the Safety and Security <br/>of Radioactive Sources [11].<br/>
<i><b>sealed source.</b></i> 'Radioactive material' that is (a) permanently sealed in a <br/>capsule or (b) closely bonded and in a solid form.<br/>
The Joint Convention on the Safety of Spent Fuel Management and on the <br/>Safety of Radioactive Waste Management definition [5] is identical, except <br/>that the words “excluding reactor 'fuel elements'” are added. The BSS <br/>definition [1] is as above11, but continues: “The capsule or material of a <i>sealed <br/>source</i> shall be strong enough to maintain leaktightness under the conditions <br/>of use and wear for which the 'source' was designed, also under foreseeable <br/>mishaps.”<br/>The term 'special form radioactive material', used in the context of 'transport' of <br/>'radioactive material', has essentially the same meaning.<br/>Disused 'sealed source': see 'Source:' 'disused source'.<br/>
<i><b>spent source.</b></i> A 'source' that is no longer suitable for its intended purpose <br/>as a result of 'radioactive' decay.<br/>
<b>!</b> Note that a 'spent source' may still represent a radiological hazard.<br/>
<i><b>unsealed source.</b></i> A 'source' that does not meet the definition of a <i>sealed <br/>source</i>.<br/>
<i><b>vulnerable source.</b></i> A 'radioactive source' for which the 'control' is <br/>inadequate to provide assurance of long term 'safety' and 'security', such that <br/>it could relatively easily be acquired by unauthorized persons.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id703skos:definition "Uranium containing the mixture of isotopes occurring in nature; uranium <br/>
depleted in the isotope 235; thorium; any of the foregoing in the form of metal, <br/>alloy, chemical compound, or concentrate; any other material containing one or <br/>
11 The definition in the BSS [1] included the word ‘bounded’ instead of ‘bonded’. <br/>
This appears to have been an error, not an intended change in meaning.<br/>
more of the foregoing in such concentration as the [IAEA] Board of <br/>Governors shall from time to time determine; and such other material as the <br/>[IAEA] Board of Governors shall from time to time determine. (From Ref. <br/>[31].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id704skos:definition "See 'monitoring' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id705skos:definition "A region within the body containing one or more radionuclides <br/>
responsible for irradiating a 'target tissue'.<br/>
Used in internal dosimetry.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id706skos:definition "The amount and isotopic composition of material released (or postulated <br/>
to be released) from a 'facility'.<br/>
Used in modelling releases of radionuclides to the environment, particularly <br/>in the context of 'accidents' at 'nuclear installations' or releases from <i>radioactive <br/>waste</i> in 'repositories'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id707skos:definition "Those provisions, approved by the 'competent authority', under which <br/>
'consignments' which do not satisfy all the applicable 'requirements' of [the <br/>Transport] Regulations may be transported. (From Ref. [2].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id708skos:definition "A facility for which predetermined facility specific actions need to be <br/>
taken if 'urgent protective actions' are ordered in its locality in the event of a <br/>'nuclear or radiological emergency'. Examples include chemical plants that <br/>cannot be evacuated until certain actions have been taken to prevent fire or <br/>explosions, and telecommunications centres that must be staffed in order to <br/>maintain telephone services. <br/>
This is not necessarily a 'facility' within the meaning of the term <i>facilities and <br/>activities</i>.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id709skos:definition "See 'nuclear material'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id71skos:definition "See 'dose concepts'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id710skos:definition "Either an indispersible solid 'radioactive material' or a sealed capsule <br/>
containing 'radioactive material'. (From Ref. [2].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id711skos:definition "See 'monitoring' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id712skos:definition "'Members of the public' for whom 'special arrangements' are necessary in <br/>
order for effective 'protective actions' to be taken in the event of a <i>nuclear or <br/>radiological emergency</i>. Examples include disabled persons, hospital patients <br/>and prisoners.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id713skos:definition "See 'activity' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id714skos:definition "1.' Nuclear fuel' removed from a reactor following irradiation that is no <br/>
longer usable in its present form because of depletion of 'fissile material', <i>poison<br/></i>buildup or 'radiation' damage.<br/>
2. ['Nuclear fuel' that has been irradiated in and permanently removed <br/>
from a reactor core.] (From Ref. [5].)<br/>
The adjective ‘spent’ suggests that 'spent fuel' cannot be used as 'fuel' in its <br/>present form (e.g. as in 'spent source'). In practice, however (as in (2) above), <br/>'spent fuel' is commonly used to refer to 'fuel' which has been used as 'fuel' but <br/>will no longer be used, whether or not it could be used (and which might more <br/>accurately be termed ‘disused 'fuel'’).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id715skos:definition "All 'activities' that relate to the handling or 'storage' of 'spent fuel', excluding <br/>
'off-site transport'. It may also involve 'discharges'. (From Ref. [5].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id716skos:definition "Any 'facility' or installation the primary purpose of which is 'spent fuel '<br/>
'management'. (From Ref. [5].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id717skos:definition "See 'source' (2).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id718skos:definition "Interested party; concerned party.<br/>
A person, company, etc., with a concern or (especially financial) interest in <br/>ensuring the success of an organization, business, system, etc.<br/>
<b>!</b> The <br/>
term <br/>
s'takeholder' has disputed usages and is misleading and too all-<br/>
encompassing for clear use. In view of the potential for misunderstanding, use <br/>of the term is discouraged in favour of ‘interested parties’ or ‘concerned <br/>parties’, for example. Interested parties would need to be specified as <br/>relevant.<br/>'Stakeholder' means an interested party — whether a person or a company, etc. <br/>— with an interest or concern in ensuring the success of an organization, <br/>business, system, etc. To ‘have a stake in’ something, figuratively, means to <br/>have something to gain or lose by, or to have an interest in, the turn of events. <br/>The term s'takeholder' is used in a broad sense to mean a person or group <br/>having an interest in the performance of an organization. Those who can <br/>influence 'events' may effectively become interested parties — whether their <br/>‘interest’ is regarded as ‘genuine’ or not — in the sense that their views need <br/>to be considered. Interested parties have typically included the following: <br/>customers, owners, 'operators', employees, 'suppliers', partners, trade unions; the <br/>regulated industry or professionals; scientific bodies; governmental agencies <br/>or regulators (local, regional and national) whose responsibilities may cover <br/>nuclear energy; the media; the public (individuals, community groups and <br/>interest groups); and other States, especially neighbouring States that have <br/>entered into agreements providing for an exchange of information concerning <br/>possible transboundary impacts, or States involved in the export or import of <br/>certain technologies or materials.<br/>The Handbook on Nuclear Law [42] states that: “Owing to the differing views <br/>on who has a genuine interest in a particular nuclear related activity, no <br/>authoritative definition of 'stakeholder' has yet been offered, and no definition <br/>is likely to be accepted by all parties. However, 'stakeholders' have typically <br/>
included the following: the regulated industry or professionals; scientific <br/>bodies; governmental agencies (local, regional and national) whose <br/>responsibilities arguably cover nuclear energy; the media; the public <br/>(individuals, community groups and interest groups); and other States <br/>(especially neighbouring States that have entered into agreements providing <br/>for an exchange of information concerning possible transboundary impacts, <br/>or States involved in the export or import of certain technologies or <br/>material).”<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id719skos:definition "A State to which a 'transboundary movement' is planned or takes place. <br/>
(From Ref. [5].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id72skos:definition "Material used to refill excavated portions of a 'repository' after 'waste' has <br/>
been emplaced.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id720skos:definition "A State from which a 'transboundary movement' is planned to be initiated <br/>
or is initiated. (From Ref. [5].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id721skos:definition "Any State, other than a 'State of origin' or a 'State of destination', through <br/>
whose territory a 'transboundary movement' is planned or takes place. (From <br/>Ref. [5].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id722skos:definition "See 'probabilistic analysis'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id723skos:definition "See 'health effects (of radiation)'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id724skos:definition "The holding of 'radioactive sources', 'spent fuel' or 'radioactive waste' in a <br/>
'facility' that provides for their/its 'containment', with the intention of retrieval. <br/>
Generalized from the Joint Convention on the Safety of Spent Fuel <br/>Management and on the Safety of Radioactive Waste Management [5], the <br/>Code of Conduct on the Safety and Security of Radioactive Sources [11] and <br/>Ref. [43].<br/>
<b>!</b> 'Storage' is by definition an interim measure, and the term <i><b>interim storage</b></i><br/>
would therefore be appropriate only to refer to short term temporary 'storage'<br/>
when contrasting this with the longer term fate of the 'waste'. 'Storage' as <br/>defined above should not be described as 'interim storage'.<br/>In many cases, the only element of this definition that is important is the <br/>distinction between 'disposal' (with no intent to retrieve) and 'storage' (with <br/>intent to retrieve). In such cases, a definition is not necessary; the distinction <br/>can be made in the form of a footnote at the first use of the term 'disposal' or <br/>'storage' (e.g. “The use of the term 'disposal' indicates that there is no intention <br/>to retrieve the 'waste'. If retrieval of the 'waste' at any time in the future is <br/>intended, the term 'storage' is used.”).<br/>For 'storage' in a combined 'storage' and 'disposal facility', for which a decision <br/>may be made at the time of its 'closure' whether to remove the 'waste' stored <br/>during the 'operation' of the 'storage' 'facility' or to dispose of it by encasing it in <br/>concrete, the question of intention of retrieval may be left open until the time <br/>of 'closure' of the 'facility'.<br/>Contrasted with 'disposal'.<br/>
<i><b>dry storage.</b></i> 'Storage' in a gaseous environment, such as air or an inert gas.<br/>
'Dry storage facilities' include 'facilities' for the 'storage' of 'spent fuel' in casks, silos <br/>or vaults.<br/>
<i><b>wet storage.</b></i> 'Storage' in water or in another liquid.<br/>
The universal mode of 'wet storage' consists in storing 'spent fuel' assemblies or <br/>'spent fuel elements' in pools of water or other liquids, usually supported on <br/>racks or in baskets and/or in 'canisters' that also contain liquid. The liquid in the <br/>pool surrounding the 'fuel' provides for heat dissipation and <i>radiation<br/></i>shielding, and the racks or other devices ensure a geometrical configuration <br/>that maintains subcriticality.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id725skos:definition "See 'radiation'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id726skos:definition "See', structures, systems and components'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id727skos:definition "A general term encompassing all of the elements (items) of a 'facility' or <br/>
'activity' which contribute to 'protection and safety', except 'human factors'.<br/>
<i><b>Structures</b></i> are the passive elements: buildings, vessels, shielding, etc. A <i><b>system<br/></b></i>comprises several 'components', assembled in such a way as to perform a <br/>specific (active) function. A <i><b>component</b></i> is a discrete element of a 'system'. <br/>
Examples of components are wires, transistors, integrated circuits, motors, <br/>relays, solenoids, pipes, fittings, pumps, tanks and valves.<br/>See also 'core components'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id728skos:definition "See 'disposal' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id729skos:definition "See 'area'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id73skos:definition "The 'dose' or 'dose rate' (or an observed measure related to the 'dose' or 'dose '<br/>
'rate') attributable to all 'sources' other than the one(s) specified.<br/>
Strictly, this applies to measurements of 'dose rate' or count rate from a sample, <br/>where the 'background dose rate 'or count rate must be subtracted from all <br/>measurements. However, 'background' is used more generally, in any situation <br/>in which a particular 'source' (or group of 'sources') is under consideration, to <br/>refer to the effects of other 'sources'. It is also applied to quantities other than <br/>'doses' or 'dose rates', such as 'activity concentrations' in environmental media.<br/>
<i><b>natural background.</b></i> The 'doses', 'dose rates' or <i>activity concentrations<br/></i>associated with 'natural sources' or any other 'sources' in the environment <br/>that are not amenable to 'control'.<br/>
This is normally considered to include 'doses', 'dose rates' or <i>activity <br/>concentrations</i> associated with 'natural sources', global fallout (but not local <br/>fallout) from atmospheric nuclear weapon tests and the Chernobyl 'accident'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id730skos:definition "Any 'legal person' to whom a 'registrant' or 'licensee' delegates duties, totally <br/>
or partially, in relation to the 'design', manufacture, production or <i>construction<br/></i>of a 'source'. (An importer of a 'source' is considered a 'supplier' of the 'source'.) <br/>(From Ref. [1].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id731skos:definition "<b>!</b> This usage is specific to the Transport Regulations, and should otherwise be <br/>
avoided.<br/>
A solid object which is not itself 'radioactive' but which has 'radioactive '<br/>
'material' distributed on its surfaces. 'SCOs' shall be in one of two groups:<br/>
(a)<br/>
<i><b>SCO-I.</b></i> A solid object on which:<br/>
(i) The 'non-fixed contamination' on the accessible surface averaged over <br/>
300 cm2 (or the area of the surface if less than 300 cm2) does not <br/>exceed 4 Bq/cm2 for beta and gamma emitters and <i>low toxicity alpha <br/>emitters</i>, or 0.4 Bq/cm2 for all other alpha emitters; and<br/>
(ii) The 'fixed contamination' on the accessible surface averaged over <br/>
300 cm2 (or the area of the surface if less than 300 cm2) does not <br/>exceed 4 × 104 Bq/cm2 for beta and gamma emitters and <i>low toxicity <br/>alpha emitters</i>, or 4 × 103 Bq/cm2 for all other alpha emitters; and<br/>
(iii) The 'non-fixed contamination' plus the 'fixed contamination' on the <br/>
inaccessible surface averaged over 300 cm2 (or the area of the surface <br/>if less than 300 cm2) does not exceed 4 × 104 Bq/cm2 for beta and <br/>
gamma emitters and 'low toxicity alpha emitters', or 4 × 103 Bq/cm2 for <br/>all other alpha emitters.<br/>
(b)<br/>
<i><b>SCO-II.</b></i> A solid object on which either the 'fixed' or <i>non-fixed <br/>contamination</i> on the surface exceeds the applicable 'limits' specified for <br/>'SCO-I' in (a) above and on which:<br/>
(i) The 'non-fixed contamination' on the accessible surface averaged over <br/>
300 cm2 (or the area of the surface if less than 300 cm2) does not <br/>exceed 400 Bq/cm2 for beta and gamma emitters and <i>low toxicity <br/>alpha emitters</i>, or 40 Bq/cm2 for all other alpha emitters; and<br/>
(ii) The 'fixed contamination' on the accessible surface, averaged over <br/>
300 cm2 (or the area of the surface if less than 300 cm2) does not <br/>exceed 8 × 105 Bq/cm2 for beta and gamma emitters and <i>low toxicity <br/>alpha emitters</i>, or 8 × 104 Bq/cm2 for all other alpha emitters; and<br/>
(iii) The 'non-fixed contamination' plus the 'fixed contamination' on the <br/>
inaccessible surface averaged over 300 cm2 (or the area of the surface <br/>if less than 300 cm2) does not exceed 8 × 105 Bq/cm2 for beta and <br/>gamma emitters and 'low toxicity alpha emitters', or 8 × 104 Bq/cm2 for <br/>all other alpha emitters. (From Ref. [2].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id732skos:definition "Periodic testing to verify that 'structures, systems and components' continue <br/>
to function or are capable of performing their functions when called upon to do <br/>so.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id733skos:definition "<i><b>area survey.</b></i> An early stage of the 'siting' 'process' for a 'repository', during <br/>which a broad region is examined to eliminate unsuitable areas and to <br/>identify other areas which may contain suitable sites.<br/>
'Area survey' is followed by 'site characterization'.<br/>'Area survey' may also refer to the 'siting' 'process' for any other <i>authorized <br/>facility</i>. See also 'site evaluation', which includes 'site characterization' and is not <br/>specific to a 'repository' site.<br/>
<i><b>habit survey.</b></i> An evaluation of those aspects of the behaviour of <i>members <br/>of the public</i> that might influence their 'exposure' — such as food <i>intake<br/></i>rates or occupancy of different areas — usually aimed at characterizing <br/>'critical groups'.<br/>
<i><b>radiological survey.</b></i> An evaluation of the radiological conditions and <br/>potential hazards associated with the production, use, transfer, release, <br/>'disposal' or presence of 'radioactive material' or other 'sources' of 'radiation'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id734skos:definition "Combined, correlated or syzygistic action of a group of units or faculties <br/>
that exceeds the sum of the individual effects; increased effectiveness, <br/>achievement, etc., produced as a result of combined action or cooperation.<br/>
The term ‘synergism’ is also used. The antonym of ‘synergic’ (synergetic, <br/>synergistic) would be ‘antergic’ (antergetic, antergistic), meaning <br/>antagonistic, e.g. of an action in opposition to the action of another part.<br/>‘Syzygy’ means a pair of connected or correlated things, such as 'safety' and <br/>'security'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id735skos:definition "See 'structures, systems and components'.<br/>
See 'structures, systems and components'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id736skos:definition "A computer 'model' that is capable of simulating the transient <br/>
performance of a complex system such as a nuclear power plant.<br/>
A 'system code' typically includes equations for thermohydraulics, neutronics <br/>and heat transfer, and must include special 'models' for simulating the <br/>performance of 'components' such as pumps and separators. The <i>system code<br/></i>typically also simulates the 'control' 'logic' implemented in the plant and is able <br/>to predict the evolution of 'accidents'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id737skos:definition "See 'validation' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id738skos:definition "See 'verification' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id739skos:definition "The systems of 'protection' for 'practices' and for 'intervention' recommended <br/>
by the International Commission on Radiological Protection.<br/>
'System of Radiological Protection' usually refers to both systems together (or, <br/>for historical reasons, to the 'system' for 'practices' only); individually they <br/>should be referred to as the ‘system of 'protection' for 'practices'’ and the ‘system <br/>of 'protection' for 'intervention'’.<br/>See Ref. [16].<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id74skos:definition "A physical obstruction that prevents or inhibits the movement of people, <br/>
radionuclides or some other phenomenon (e.g. fire), or provides shielding <br/>against 'radiation'.<br/>
See also 'cladding (material)', 'containment', 'defence in depth'.<br/>
<i><b>intrusion barrier.</b></i> 'Components' of a 'repository' designed to prevent <br/>inadvertent access to the 'waste' by humans, animals or plants.<br/>
<i><b>multiple barriers.</b></i> Two or more natural or engineered 'barriers' used to <br/>isolate 'radioactive waste' in, and prevent 'migration' of radionuclides from, <br/>a 'repository'.<br/>
<b>!</b> The term ‘chemical 'barrier'’ is sometimes used in the context of 'waste disposal'<br/>
to describe the chemical effect of a material that enhances the extent to which <br/>radionuclides react chemically with the material or with the host rock, thus <br/>inhibiting the 'migration' of the radionuclides. As defined above, this is not <br/>
strictly a 'barrier' (unless the material also constitutes a physical 'barrier'), but <br/>the effect may be equivalent to that of a 'barrier', and it may therefore be <br/>convenient to regard it as such.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id740skos:definition "The residues resulting from the processing of ore to extract 'uranium series' or <br/>
'thorium series 'radionuclides, or similar residues from processing ores for other purposes.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id741skos:definition "A 'tank' container, a portable 'tank', a road 'tank' 'vehicle', a rail 'tank' wagon or <br/>
a receptacle with a capacity of not less than 450 L for containing liquids, <br/>powders, granules, slurries or solids which are loaded as gas or liquid and <br/>subsequently solidified, and of not less than 1000 L for containing gases. A <i>tank<br/></i>container shall be capable of being carried on land or on sea and of being <br/>loaded and discharged without the need of removal of its structural equipment, <br/>shall possess stabilizing members and tie-down attachments external to the <br/>shell, and shall be capable of being lifted when full. (From Ref. [2].)<br/>
<b>!</b> This usage is specific to the Transport Regulations [2], and should otherwise <br/>
be avoided.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id742skos:definition "The tissue or organ to which 'radiation' is directed.<br/>
Used in internal dosimetry, normally in relation to a 'source region'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id743skos:definition "See 'monitoring' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id744skos:definition "See 'ageing: non-physical ageing'.<br/>
See 'ageing: non-physical ageing'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id745skos:definition "See 'relocation'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id746skos:definition "The use of organized intimidation; a policy intended to strike with terror <br/>those against whom it is adopted; the employment of methods of intimidation; <br/>the fact of terrorizing or condition of being terrorized.<br/>
The United Nations High-level Panel on Threats, Challenges and Change <br/>(Ref. [44], p. 183) has stated the following: <br/>
“164. That definition of 'terrorism' should include the following elements: (a) <br/>recognition, in the preamble, that State use of force against civilians is regulated <br/>by the Geneva Conventions and other instruments, and, if of sufficient scale, <br/>constitutes a war crime by the persons concerned or a crime against humanity; <br/>(b) restatement that acts under the 12 preceding anti-terrorism conventions are <br/>'terrorism', and a declaration that they are a crime under international law; and <br/>restatement that 'terrorism' in time of armed conflict is prohibited by the Geneva <br/>Conventions and Protocols; (c) reference to the definitions contained in the <br/>1999 International Convention for the Suppression of the Financing of <br/>Terrorism and Security Council resolution 1566 (2004); (d) description of <br/>'terrorism' as “any action, in addition to actions already specified by the existing <br/>conventions on aspects of 'terrorism', the Geneva Conventions and Security <br/>Council resolution 1566 (2004), that is intended to cause death or serious bodily <br/>harm to civilians or non-combatants, when the purpose of such act, by its nature <br/>or context, is to intimidate a population, or to compel a Government or an <br/>international organization to do or to abstain from doing any act”. <br/>See http://www.un.org/secureworld/report2.pdf<br/>
[<i><b>nuclear terrorism.</b></i> 'Terrorism' involving 'nuclear material'.] (See 'nuclear'.)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id747skos:definition "Avoid these and similar journalese terms such as 'nuclear sabotage' or <i>nuclear <br/>trafficking</i> in publications.<br/>
[<i><b>radiological terrorism.</b></i> 'Terrorism' involving 'radioactive material'.]<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id748skos:definition "Avoid these and similar journalese terms such as 'radiological sabotage' or <br/>radiological trafficking in publications.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id749skos:definition "Anyone who attempts to further his or her views by a system of coercive <br/>intimidation; a person who uses or favours violent and intimidating methods <br/>of coercing a government or community.<br/>The term now usually refers to a member of a clandestine or expatriate <br/>organization aiming to coerce an established government by acts of violence <br/>against it or its subjects.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id75skos:definition "The SI unit of 'activity', equal to one transformation per second.<br/>
Supersedes the non-SI unit 'curie (Ci)'. 1 Bq = 27 pCi (2.7 × 10–11 Ci) <br/>approximately. 1 Ci = 3.7 × 1010 Bq.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id750skos:definition "See 'terrorism'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id751skos:definition "See 'exposure, types of:' 'medical exposure'.<br/>
See 'exposure, types of:' 'medical exposure'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id752skos:definition "The decay chain of thorium-232.<br/>
Namely, thorium-232, radium-228, actinium-228, thorium-228, radium-224, <br/>radon-220, polonium-216, lead-212, bismuth-212, polonium-212 (64%), <br/>thallium-208 (36%) and (stable) lead-208.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id753skos:definition "Radon-220.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id754skos:definition "The (short lived) 'radioactive' decay products of 'thoron'.<br/>
Namely, polonium-216 (sometimes called thorium A), lead-212 (thorium B), <br/>bismuth-212 (thorium C), polonium-212 (thorium C′, 64%) and thallium-208 <br/>(thorium C″, 36%). The stable decay product lead-208 is sometimes known as <br/>thorium D.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id755skos:definition "See 'assessment' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id756skos:definition "See 'maintenance: periodic maintenance'.<br/>
See 'maintenance: periodic maintenance'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id757skos:definition "Material designed to have, when irradiated, interaction properties similar <br/>
to those of soft tissue.<br/>
Used to make phantoms, such as the 'ICRU sphere'.<br/>
The 'tissue equivalent material' used in the 'ICRU sphere' has a density of 1 g/cm3<br/>and an elemental composition, by mass, of 76.2% oxygen, 11.1% carbon, 10.1% <br/>hydrogen and 2.6% nitrogen, but materials of various other compositions (e.g. <br/>water) are considered suitable for particular applications [17].<br/>The term <i><b>tissue substitute</b></i> is also used with the same meaning.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id758skos:definition "See 'tissue equivalent material'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id759skos:definition "Multiplier of the 'equivalent dose' to an organ or tissue used for 'radiation '<br/>
'protection' purposes to account for the different sensitivities of different organs <br/>and tissues to the induction of 'stochastic effects' of 'radiation'. (From Ref. [1].)<br/>
The 'tissue weighting factors' recommended by the International Commission <br/>on Radiological Protection for calculating 'effective dose' are:<br/>
Tissue or organ<br/>
' w'T<br/>
Gonads<br/>
0.20<br/>
Bone marrow (red)<br/>
0.12<br/>
Colona<br/>
0.12<br/>
Lung<br/>
0.12<br/>
Stomach<br/>
0.12<br/>
Bladder<br/>
0.05<br/>
Breast<br/>
0.05<br/>
Liver<br/>
0.05<br/>
Oesophagus<br/>
0.05<br/>
Thyroid<br/>
0.05<br/>
Skin<br/>
0.01<br/>
Bone surface<br/>
0.01<br/>
Remainderb<br/>
0.05<br/>
a The weighting factor for the colon is applied to <br/>
the mass average of the 'equivalent dose' in the <br/>walls of the upper and lower large intestine.<br/>
b For the purposes of calculation, the <br/>
remainder is composed of adrenal glands, <br/>brain, extrathoracic region, small intestine, <br/>kidney, muscle, pancreas, spleen, thymus <br/>and uterus. In those exceptional cases in <br/>which the most exposed remainder tissue <br/>receives the highest <i>committed equivalent <br/>dose</i> of all organs, a weighting factor of 0.025 <br/>shall be applied to that tissue or organ and a <br/>weighting factor of 0.025 to the average <i>dose<br/></i>in the rest of the remainder as defined here.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id76skos:definition "See 'plant states'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id760skos:definition "See 'illicit trafficking'.<br/>
See 'illicit trafficking'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id761skos:definition "See 'illicit trafficking'.<br/>
See 'illicit trafficking'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id762skos:definition "'Exposure' of 'members of the public' in one State due to 'radioactive '<br/>
'material' released via 'accidents', 'discharges' or 'waste disposal' in another State.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id763skos:definition "1. Any movement of 'radioactive material' from one State to or through <br/>
another.<br/>
2. [Any 'shipment' of 'spent fuel' or of 'radioactive waste' from a 'State of '<br/>
'origin' to a 'State of destination'.] (From Ref. [5].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id764skos:definition "Those 'members of the public' who are residing for a short period of time <br/>
(days to weeks) in a location (such as a camping ground) that can be identified <br/>in advance. This does not include 'members of the public' who may be travelling <br/>through an area.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id765skos:definition "See 'exposure situations: chronic exposure'.<br/>
See 'exposure situations: chronic exposure'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id766skos:definition "See 'emergency'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id767skos:definition "1. The deliberate physical movement of 'radioactive material' (other than <br/>
that forming part of the means of propulsion) from one place to another.<br/>
The term <i><b>transportation</b></i> is also used, particularly in US English or where <br/>there is a need to distinguish this meaning of 'transport' from meaning (2).<br/>
<i><b>international nuclear transport.</b></i> [The carriage of a 'consignment' of <br/>'nuclear material' by any means of 'transportation' intended to go beyond <br/>the territory of the State where the 'shipment' originates, beginning with <br/>the departure from a 'facility' of the shipper in that State and ending with <br/>the arrival at a 'facility' of the receiver within the State of ultimate <br/>destination.]. (From Ref. [30].)<br/>
More recent texts use the term 'transboundary movement' for a similar <br/>concept.<br/>
2. The movement of something as a result of being carried by a medium.<br/>
A general term used when a number of different 'processes' are involved. The <br/>most common examples are heat 'transport —' a combination of 'advection', <br/>convection, etc., in a cooling medium — and radionuclide 'transport' in the <br/>environment — which could include 'processes' such as 'advection', 'diffusion', <br/>'sorption' and 'uptake'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id768skos:definition "A number assigned to a 'package', 'overpack' or 'freight container', or to <br/>
unpackaged 'LSA-I' or 'SCO-I', which is used to provide 'control' over <i>radiation<br/>exposure</i>. (From Ref. [2].)<br/>
The value of the 'transport index' for a 'package' or 'overpack' is used (with the <br/>surface 'dose rate') in determining the category (I-WHITE, II-YELLOW or <br/>III-YELLOW) to which the 'package' or 'overpack' belongs, and hence which <br/>'requirements' are applicable to its 'transport'. A 'package' or 'overpack' with a <br/>'transport index' greater than 10 can be transported only under 'exclusive use'.<br/>The 'procedure' for calculating a 'transport index' is given in paras 526 and 527 of <br/>the 2005 edition of the Transport Regulations [2]. In essence, the <i>transport <br/>index</i> is the maximum 'dose rate' 1 m from the outer surface of the load, <br/>expressed in mrem/h (or the value in mSv/h multiplied by 100), and in <br/>specified cases multiplied by a factor between 1 (for small sized loads) and 10 <br/>(for large sized loads). (See Ref. [2].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id769skos:definition "See 'transport' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id77skos:definition "Any 'procedure' used to determine the nature, 'activity', location or <br/>
retention of radionuclides in the body by direct (in vivo) measurement or by in <br/>vitro analysis of material excreted or otherwise removed from the body.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id770skos:definition "See 'waste management, radioactive' (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id771skos:definition "See 'package'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id772skos:definition "See 'exposure, types of'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id773skos:definition "A medium into which the transferred' residual heat' can always be <br/>
accepted, even if all other means of removing the heat have been lost or are <br/>insufficient.<br/>
This medium is normally a body of water or the atmosphere.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id774skos:definition "The 'systems' and 'components' needed to transfer 'residual heat' to the <br/>
'ultimate heat sink' after shutdown.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id775skos:definition "The fraction of 'potential alpha energy' of 'radon progeny' that arises from <br/>
atoms that are not attached to ambient aerosol particles.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id776skos:definition "See 'analysis'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id777skos:definition "See 'approval'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id778skos:definition "See 'nuclear fuel'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id779skos:definition "Thorium containing not more than 10–7 g of uranium-233 per gram of <br/>
thorium-232. (From Ref. [2].)<br/>
Although the term 'unirradiated thorium' is used, the issue is not really whether <br/>the thorium has been irradiated, but rather whether the content of uranium-<br/>233 (a 'fissile material') is significantly higher than the trace levels found in <br/>naturally occurring thorium.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id78skos:definition "See 'half-life' (2).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id780skos:definition "Uranium containing not more than 2 × 103 Bq of plutonium per gram of <br/>
uranium-235, not more than 9 × 106 Bq of 'fission products' per gram of uranium-<br/>235 and not more than 5 × 10–3 g of uranium-236 per gram of uranium-235. <br/>(From Ref. [2].)<br/>
Although the term 'unirradiated uranium' is used, the issue is not really <br/>whether the uranium has been irradiated, but rather whether the content of <br/>plutonium (a 'fissile material') is significantly higher than the trace levels found <br/>in naturally occurring uranium.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id781skos:definition "See 'linear energy transfer (LET)'.<br/>
See 'linear energy transfer (LET)'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id782skos:definition "See 'use'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id783skos:definition "See 'source' (2).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id784skos:definition "1. A general term for the 'processes' by which radionuclides enter one part <br/>
of a biological system from another.<br/>
Used for a range of situations, particularly for describing the overall effect <br/>when there are a number of contributing 'processes'; e.g. <i><b>root uptake</b></i>, the <br/>transfer of radionuclides from soil to plants through the plant roots.<br/>
2. The 'processes' by which radionuclides enter the body fluids from the <br/>
respiratory tract, gastrointestinal tract or through the skin, or the fraction of an <br/>'intake' that enters the body fluids by these 'processes'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id785skos:definition "<i><b>depleted uranium.</b></i> Uranium containing a lesser mass percentage of <br/>uranium-235 than in 'natural uranium'. (From Ref. [2].)<br/>
<i><b>enriched uranium.</b></i> Uranium containing a greater mass percentage of <br/>uranium-235 than 0.72%. (From Ref. [2].)<br/>
<i><b>high enriched uranium (HEU).</b></i> Uranium containing 20% or more of the <br/>isotope 235U. 'HEU' is considered a 'special fissionable material' and a direct <br/>use material. (From Ref. [32].)<br/>
<i><b>low enriched uranium (LEU).</b></i> 'Enriched uranium' containing less than <br/>20% of the isotope 235U. 'LEU' is considered a <i>special fissionable material<br/></i>and an indirect use material. (From Ref. [32].)<br/>
<i><b>natural uranium.</b></i> Uranium (which may be chemically separated) <br/>containing the naturally occurring distribution of uranium isotopes <br/>(approximately 99.28% uranium-238 and 0.72% uranium-235 by mass). <br/>(From Ref. [2].)<br/>
In all cases, a very small mass percentage of uranium-234 is present.<br/>The naturally occurring distribution of uranium isotopes including uranium-<br/>234 (approximately 99.285% uranium-238, 0.710% uranium-235 and 0.005% <br/>uranium-234 by mass) corresponds to approximately 48.9% uranium-234, <br/>2.2% uranium-235 and 48.9% uranium-238 by 'activity'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id786skos:definition "Uranium containing the isotope uranium-235 or uranium-233 or both in <br/>
an amount such that the abundance ratio of the sum of these isotopes to the <br/>isotope uranium-238 is greater than the ratio of the isotope uranium-235 to the <br/>isotope uranium-238 occurring in nature [30, 31].<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id787skos:definition "The decay chain of uranium-238.<br/>
Namely, uranium-238, thorium-234, protactinium-234, uranium-234, <br/>thorium-230, radium-226, radon-222, polonium-218, lead-214, bismuth-214 <br/>and polonium-214, lead-210, bismuth-210, polonium-210 and (stable) <br/>lead-206, plus traces of astatine-218, thallium-210, lead-209, mercury-206 and <br/>thallium-206.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id788skos:definition "See 'protective action' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id789skos:definition "See 'emergency zones'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id79skos:definition "That part of the environment normally inhabited by living organisms.<br/>
In practice, the 'biosphere' is not usually defined with great precision, but is <br/>generally taken to include the atmosphere and the Earth’s surface, including <br/>the soil and surface water bodies, seas and oceans and their sediments. There <br/>is no generally accepted definition of the depth below the surface at which soil <br/>or sediment ceases to be part of the 'biosphere', but this might typically be <br/>taken to be the depth affected by basic human actions, in particular farming.<br/>In 'waste safety' in particular, the 'biosphere' is normally distinguished from the <br/>'geosphere'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id790skos:definition "<i><b>authorized use.</b></i> Use of 'radioactive material' or 'radioactive' objects from an <br/>authorized' practice' in accordance with an 'authorization'.<br/>
Intended primarily for contrast with 'clearance', in that 'clearance' implies no <br/>further 'regulatory control' over the use, whereas the 'authorization' for <br/>'authorized use' may prescribe or prohibit specific uses.<br/>A form of 'restricted use'.<br/>
<i><b>restricted use.</b></i> The use of an area or of materials subject to restrictions <br/>imposed for reasons of 'radiation protection and safety'.<br/>
Restrictions would typically be expressed in the form of prohibition of <br/>particular 'activities' (e.g. house building, growing or harvesting particular <br/>foods) or prescription of particular 'procedures' (e.g. materials may only be <br/>recycled or reused within a 'facility').<br/>
<i><b>unrestricted use.</b></i> The use of an area or of material without any <br/>radiologically based restrictions.<br/>
<b>!</b> There may be other restrictions on the use of the area or material, such as <br/>
planning restrictions on the use of an area of land or restrictions related to the <br/>chemical properties of a material. In some situations, these restrictions could, <br/>in addition to their primary intended effect, have an incidental effect on <br/>'radiation' 'exposure', but the use is classified as 'unrestricted use' unless the <br/>primary reason for the restrictions is radiological.<br/>'Unrestricted use' is contrasted with 'restricted use'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id791skos:definition "1. The 'process' of determining whether a product or service is adequate to <br/>
perform its intended function satisfactorily.<br/>
'Validation' is broader in scope, and may involve a greater element of <br/>judgement, than 'verification'.<br/>
<i><b>computer system validation.</b></i> The 'process' of testing and evaluating the <br/>integrated computer 'system' (hardware and software) to ensure <br/>compliance with the functional, performance and interface requirements.<br/>
<i><b>model validation.</b></i> The 'process' of determining whether a 'model' is an <br/>adequate representation of the real 'system' being modelled, by comparing <br/>the predictions of the 'model' with observations of the real 'system'.<br/>
Normally contrasted with 'model verification', although 'verification' will often <br/>be a part of the broader 'process' of 'validation'.<br/>There is some controversy about the extent to which 'model validation' can be <br/>achieved, particularly in relation to modelling the long term 'migration' of <br/>radionuclides from 'radioactive waste' in 'repositories'.<br/>
<i><b>system code validation.</b></i> 'Assessment' of the accuracy of values predicted <br/>by the 'system code' against relevant experimental data for the important <br/>phenomena expected to occur.<br/>
2. Confirmation by means of objective evidence that the requirements <br/>
for a specific intended purpose and use or application have been fulfilled. See <br/>'verification'. <br/>
The corresponding status is termed ‘validated’.<br/>The conditions of use for 'validation' purposes may be real or simulated.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id792skos:definition "A road 'vehicle' (including an articulated 'vehicle', i.e. a tractor and semi-<br/>
trailer combination) or railroad car or railway wagon. Each trailer shall be <br/>considered a separate 'vehicle'. (From Ref. [2].)<br/>
<b>!</b> This usage is specific to the Transport Regulations [2], and should otherwise <br/>
be avoided.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id793skos:definition "A 'design', contracting or manufacturing organization supplying a service, <br/>
'component' or 'facility'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id794skos:definition "1. The 'process' of determining whether the quality or performance of a <br/>
product or service is as stated, as intended or as required.<br/>
'Verification' is closely related to 'quality assurance' and 'quality control'.<br/>
<i><b>computer system verification.</b></i> The 'process' of ensuring that a phase in the <br/>'system' life cycle meets the requirements imposed on it by the previous <br/>phase.<br/>
<i><b>model verification.</b></i> The 'process' of determining whether a <i>computational <br/>model</i> correctly implements the intended 'conceptual model' or <br/>'mathematical model'.<br/>
<i><b>system code verification</b></i><b>.</b> Review of source coding in relation to its <br/>description in the 'system code' documentation.<br/>
2. Confirmation by means of objective evidence that specified <br/>
requirements have been fulfilled. See 'validation.'<br/>
The corresponding status is termed ‘verified’.<br/>'Verification' may comprise 'activities' such as: performing alternative <br/>calculations; comparing a new 'design' specification with a similar proven <br/>'design' specification; undertaking tests and demonstrations; and reviewing <br/>documents prior to issue.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id795skos:definition "See 'waste classes'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id796skos:definition "Any seagoing 'vessel' or inland waterway craft used for carrying cargo. <br/>
(From Ref. [2].)<br/>
<b>!</b> This restricted use of the term 'vessel' in relation to the 'transport 'of 'radioactive '<br/>
'material' does not apply in other areas of 'safety', e.g. a reactor pressure vessel is <br/>a vessel as normally understood.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id797skos:definition "See 'waste management, radioactive' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id798skos:definition "See 'source' (2).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id799skos:definition "A contact point that is staffed or able to be alerted at all times for <br/>
promptly responding to, or initiating a response to, an incoming <i>notification<br/></i>(definition (2)), warning message, request for assistance or request for <br/>'verification' of a message, as appropriate, from the IAEA.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id8skos:definition "See 'limit'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id80skos:definition "Any substance placed around a 'waste package' in a 'repository' to serve as a <br/>
'barrier' to restrict the access of groundwater to the 'waste package' and to reduce <br/>by 'sorption' and precipitation' 'the rate of eventual 'migration' of radionuclides <br/>from the 'waste'.<br/>
The above definition is clearly specific to 'waste safety'. The term 'buffer' (e.g. in <br/>'buffer' solution) is also used, in its normal scientific sense (and therefore <br/>normally without specific definition), in a variety of contexts.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id800skos:definition "Material for which no further use is foreseen.<br/>
<i><b>exempt waste.</b></i> 'Waste' that is released from 'regulatory control' in <br/>accordance with 'exemption' principles.<br/>
<b>['mining and milling waste (MMW).'</b> 'Waste' from 'mining and milling.']<br/>
This includes 'tailings' from' 'processing, residues from heap leaching, waste <br/>rock, sludges, filter cakes, scales and various effluents.<br/>
<b>!</b> See also ['mining and milling'].<br/>
<i><b>mixed waste.</b></i> 'Radioactive waste' that also contains non-radioactive toxic <br/>or hazardous substances.<br/>
<i><b>NORM waste.</b></i> 'Naturally occurring radioactive material' for which no <br/>further use is foreseen.<br/>
<i><b>radioactive waste.</b></i> See 'waste, radioactive'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id801skos:definition "1. For legal and regulatory purposes, 'waste' that contains, or is <br/>
contaminated with, radionuclides at concentrations or 'activities' greater than <br/>'clearance' 'levels' as established by the 'regulatory body'.<br/>
<b>!</b> It should be recognized that this definition is purely for regulatory purposes, <br/>
and that material with 'activity concentrations' equal to or less than <i>clearance <br/>levels</i> is 'radioactive' from a physical viewpoint, although the associated <br/>radiological hazards are considered negligible.<br/>'Waste' should be used in the singular unless reference is expressly being made <br/>to the presence of various types of 'waste'.<br/>
2. ['Radioactive material' in gaseous, liquid or solid form for which no <br/>
further use is foreseen by the Contracting Party or by a natural or <i>legal person<br/></i>whose decision is accepted by the Contracting Party, and which is controlled as <br/>'radioactive' 'waste' by a 'regulatory body' under the legislative and regulatory <br/>framework of the Contracting Party.] (From Ref. [5].)<br/>
3. Material, whatever its physical form, remaining from 'practices' or <br/>
'interventions' and for which no further use is foreseen (i) that contains or is <br/>contaminated with 'radioactive' substances and has an 'activity' or <i>activity <br/>concentration</i> higher than the level for 'clearance' from regulatory 'requirements', <br/>and (ii) 'exposure' to which is not 'excluded' from the [Basic Safety] Standards. <br/>(From Ref. [1].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id802skos:definition "Quantitative or qualitative criteria specified by the 'regulatory body', or <br/>
specified by an 'operator' and 'approved' by the 'regulatory body', for <i>radioactive <br/>waste</i> to be accepted by the 'operator' of a 'repository' for 'disposal', or by the <br/>'operator' of a 'storage facility' for 'storage'.<br/>
'Waste acceptance requirements' might include, for example, restrictions on the <br/>'activity' 'concentration' or total 'activity' of particular radionuclides (or types of <br/>radionuclide) in the 'waste', or 'requirements' concerning the 'waste form' or <br/>'packaging' of the 'waste'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id803skos:definition "See 'container, waste'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id804skos:definition "See 'characterization' (2).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id805skos:definition "High level waste<br/>
[HGW]: mainly HLW<br/>
[ILW] <br/>
Radioactive<br/>
Increasing<br/>
waste <br/>
activity<br/>
concentration<br/>
Low and intermediate<br/>
[LLW] <br/>
level waste<br/>
Exempt waste<br/>
Classes not in square brackets are those recommended in Ref. [45]. This <br/>classification system is organized to take into account matters considered of <br/>prime importance for 'disposal safety'. A number of issues related to <i>waste<br/></i>classification are currently under review.<br/>The other classes listed below (in square brackets) are sometimes used, e.g. in <br/>national classification systems, and are mentioned here to indicate how they <br/>typically relate to the classes in Ref. [45].<br/>Other systems classify 'waste' on other bases, such as according to its origin <br/>(e.g. reactor 'operations' 'waste', 'reprocessing' 'waste', 'decommissioning' 'waste' and <br/>defence 'waste').<br/>
<i><b>exempt waste. </b></i>See' waste.'<br/>
<b>['heat generating waste (HGW)'</b><b>]'.'</b> 'Radioactive waste' that is sufficiently <br/>'radioactive' that the decay heat significantly increases its temperature and <br/>the temperature of its surroundings.<br/>
In practice, 'heat generating waste' is normally 'high level waste', although some <br/>types of 'intermediate level waste' may qualify as 'heat generating waste'.<br/>
<i><b>high level waste (HLW).</b></i> The 'radioactive' liquid containing most of the <br/>'fission products' and actinides present in 'spent fuel' — which forms the <br/>residue from the first solvent extraction cycle in 'reprocessing' — and some <br/>of the associated 'waste' streams; this material following solidification; <br/>'spent fuel' (if it is declared a 'waste'); or any other 'waste' with similar <br/>radiological characteristics.<br/>
Typical characteristics of 'high level waste' are thermal power above about <br/>2 kW/m3 and long lived radionuclide concentrations exceeding the limitations <br/>for 'short lived waste' [45].<br/>
<b>['intermediate level waste (ILW)'</b><b>]'.'</b> See <i>low and intermediate level waste <br/>(LILW)</i>.<br/>
<i><b>long lived waste.</b></i> 'Radioactive waste' that contains significant levels of <br/>radionuclides with a 'half-life' greater than 30 years.<br/>
Typical characteristics are long lived radionuclide concentrations exceeding <br/>the limitations for 'short lived waste' [45].<br/>
<i><b>low and intermediate level waste (LILW).</b></i> 'Radioactive waste' with <br/>radiological characteristics between those of 'exempt waste' and <i>high level <br/>waste</i>. This may be 'long lived waste' <i><b>(LILW-LL)</b></i> or <i>short lived waste<br/><b>(LILW-SL)</b></i>.<br/>
Typical characteristics of 'low and intermediate level waste 'are 'activity' levels <br/>above 'clearance levels' and thermal power below about 2 kW/m3 [45].<br/>Many States subdivide this class in other ways, for example into <i><b>low level <br/>waste (LLW)</b></i> and <i><b>intermediate level waste (ILW)</b></i> or <i><b>medium level waste <br/>(MLW)</b></i>, often on the basis of 'waste acceptance requirements' for <i>near surface <br/>repositories</i>. These terms should not be used in 'IAEA publications' unless <br/>explicit definitions are given for the purposes of the publication in question.<br/>
<b>['low level waste (LLW)'</b><b>]'.'</b> See 'low and intermediate level waste (LILW)'.<br/>
<b>['medium level waste (MLW)'</b><b>]'.'</b> See <i>low and intermediate level waste <br/>(LILW)</i>.<br/>
<i><b>short lived waste.</b></i> 'Radioactive waste' that does not contain significant <br/>levels of radionuclides with a 'half-life' greater than 30 years.<br/>
Typical characteristics are restricted long lived radionuclide concentrations <br/>(limitation of long lived radionuclides to 4000 Bq/g in individual <i>waste <br/>packages</i> and to an overall average of 400 Bq/g per 'waste package'); see paras <br/>324 and 325 of Ref. [45].<br/>
<b>['very low level waste (VLLW)'</b><b>]'.'</b> ['Radioactive waste' considered suitable <br/>by the 'regulatory body' for 'authorized disposal', subject to specified <br/>conditions, with ordinary 'waste' in 'facilities' not specifically designed for <br/>'radioactive waste disposal'.]<br/>
This is a category used in some Member States; in others there is no such <br/>category, as no 'radioactive' 'waste' at all may be disposed of in this way, however <br/>low level it is.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id806skos:definition "See 'waste management, radioactive' (1).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id807skos:definition "See 'container, waste'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id808skos:definition "See 'disposal'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id809skos:definition "'Waste' in its physical and chemical form after 'treatment' and/or <br/>
'conditioning' (resulting in a solid product) prior to 'packaging'. The 'waste form' is <br/>a 'component' of the 'waste package'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id81skos:definition "Neutron absorbing material, used to control 'reactivity', with particular <br/>
capability of being depleted by neutron 'absorption'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id810skos:definition "The 'operating organization' of a 'facility or activity' that generates 'waste'.<br/>
<b>!</b> For convenience, the scope of the term 'waste generator' is sometimes extended <br/>
to include whoever currently has the responsibilities of the <i>waste generator<br/></i>(e.g. if the actual 'waste generator' is unknown or no longer exists and a <br/>successor organization has assumed responsibility for the 'waste').<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id811skos:definition "1. All administrative and operational 'activities' involved in the handling, <br/>
'pretreatment', 'treatment', 'conditioning', 'transport', 'storage' and 'disposal' of <br/>'radioactive waste'.<br/>
Radioactive waste<br/>
management<br/>
Predisposal<br/>
Disposal<br/>
Processing<br/>
Storage<br/>
Transport <br/>
Pretreatment<br/>
Treatment <br/>
Conditioning<br/>
Segregation Decontamination<br/>
Activity<br/>
Immobilization<br/>
Overpack<br/>
removal<br/>
Collection<br/>
Chemical<br/>
Volume<br/>
Change of<br/>
Packaging<br/>
adjustment<br/>
reduction<br/>
composition<br/>
<i><b>conditioning.</b></i> Those 'operations' that produce a 'waste package' suitable for <br/>handling, 'transport', 'storage' and/or 'disposal'. 'Conditioning' may include the <br/>conversion of the 'waste' to a solid 'waste form', enclosure of the 'waste' in <br/>containers and, if necessary, provision of an 'overpack'.<br/>
<i><b>immobilization.</b></i> Conversion of 'waste' into a 'waste form' by solidification, <br/>embedding or encapsulation.<br/>
'Immobilization' reduces the potential for 'migration' or 'dispersion' of <br/>radionuclides during handling, 'transport', 'storage' and/or 'disposal'.<br/>
<i><b>overpack.</b></i> A secondary (or additional) outer container for one or more <br/>'waste packages', used for handling, 'transport', 'storage' and/or 'disposal'.<br/>
<i><b>packaging.</b></i> Preparation of 'radioactive waste' for safe handling, 'transport', <br/>'storage' and/or 'disposal' by means of enclosing it in a suitable 'container'. <br/>
<i><b>predisposal.</b></i> Any 'waste management' steps carried out prior to 'disposal', <br/>such as 'pretreatment', 'treatment', 'conditioning', 'storage' and <i>transport <br/>activities</i>.<br/>
'Predisposal' is used as a contraction of ‘pre-disposal <i>radioactive waste <br/>management</i>’, not a form of 'disposal'. <br/>
<i><b>pretreatment.</b></i> Any' 'or all of the 'operations' prior to 'waste treatment', such as <br/>collection, 'segregation', chemical adjustment and 'decontamination'.<br/>
<i><b>processing.</b></i> Any 'operation' that changes the characteristics of 'waste', <br/>including 'pretreatment', 'treatment' and 'conditioning'.<br/>
<i><b>segregation.</b></i> An activity where types of 'waste' or material ('radioactive' or <br/>'exempt') are separated or are kept separate on the basis of radiological, <br/>chemical and/or physical properties, to facilitate 'waste' handling and/or <br/>'processing'.<br/>
<i><b>treatment.</b></i> 'Operations' intended to benefit 'safety' and/or economy by <br/>changing the characteristics of the 'waste'. Three basic 'treatment' objectives <br/>are:<br/>
(a) 'Volume reduction';<br/>(b) Removal of radionuclides from the 'waste'; <br/>(c) Change of composition.<br/>
'Treatment' may result in an appropriate 'waste form'.<br/>
If 'treatment' does not result in an appropriate 'waste form', the 'waste' may be <br/>immobilized.<br/>
<i><b>volume reduction.</b></i> A 'treatment' method that decreases the physical <br/>volume of a 'waste'.<br/>
Typical 'volume reduction' methods are mechanical compaction, incineration <br/>and evaporation.<br/>Should not be confused with 'waste minimization'.<br/>
2. [All 'activities', including 'decommissioning' 'activities', that relate to the <br/>
handling, 'pretreatment', 'treatment', 'conditioning', 'storage' or 'disposal' of <br/>'radioactive waste', excluding 'off-site transportation'. It may also involve <br/>'discharges'.] (From Ref. [5].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id812skos:definition "1. 'Facility' specifically designated to handle, treat, condition, temporarily <br/>
store or permanently dispose of 'radioactive waste'. (From Ref. [1].)<br/>
2. [Any 'facility' or 'installation' the primary purpose of which is 'radioactive '<br/>
'waste management', including a 'nuclear facility' in the 'process' of being <br/>'decommissioned' only if it is designated by the Contracting Party as a <br/>'radioactive waste management facility'.] (From Ref. [5].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id813skos:definition "See 'minimization, waste.'<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id814skos:definition "See 'package, waste'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id815skos:definition "See 'radiation: strongly penetrating radiation'.<br/>
See 'radiation: strongly penetrating radiation'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id816skos:definition "See 'storage'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id817skos:definition "See 'plant states'.<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id818skos:definition "Any person who works, whether full time, part time or temporarily, for an <br/>
'employer' and who has recognized rights and duties in relation to occupational <br/>'radiation protection'. (A self-employed person is regarded as having the duties <br/>of both an 'employer' and a 'worker'.) (From Ref. [1].)<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id819skos:definition "A unit of 'potential alpha energy' concentration (i.e. the 'potential alpha '<br/>
'energy' per unit volume of air) resulting from the presence of 'radon progeny' or <br/>'thoron progeny', equal to 1.3 × 108 MeV/m3 (exactly).<br/>
<b>!</b> The <br/>
term <br/>
'working level' is now obsolete and its use is discouraged.<br/>
In SI units, a 'working level' is 2.1 × 10–5 J/m3 (approximately).<br/>" (en)
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http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id82skos:definition "See 'burnable absorber' and 'poison'.<br/>
See 'burnable absorber' and 'poison'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id820skos:definition "The 'exposure' to 'radon progeny' or 'thoron progeny' which would be <br/>
incurred during a working month (170 hours) in a constant <i>potential alpha <br/>energy</i> concentration of one 'working level'.<br/>
<b>!</b> The <br/>
term <br/>
'working level month' is now obsolete and its use is discouraged.<br/>
In SI units, a 'working level month' is 3.54 × 10–3 J·h/m3 (approximately).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id821skos:definition "See <i>monitoring</i> (1).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id83skos:definition "1. A device to inhibit, deliberately but temporarily, the functioning of a <br/>
circuit or 'system' by, for example, short circuiting the contacts of a relay.<br/>
<i><b>maintenance bypass.</b></i> A 'bypass' of 'safety system' equipment during <br/>'maintenance', testing or 'repair'.<br/>
<i><b>operational bypass.</b></i> A 'bypass' of certain 'protective actions' when they are <br/>not necessary in a particular mode of plant 'operation'.<br/>
<b>!</b> An <br/>
'operational bypass' may be used when the 'protective action' prevents, or <br/>
might prevent, reliable 'operation' in the required mode.<br/>
2. A route that allows 'fission products' released from a reactor core to <br/>
enter the environment without passing through the 'containment' or other <br/>enclosure designed to confine and reduce a release in the event of an <br/>'emergency'.<br/>
This route may be established intentionally by the 'operator' or as a result of <br/>the 'event'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id84skos:definition "A measurement of, or adjustment to, an instrument, 'component' or 'system'<br/>
to ensure that its accuracy or response is acceptable.<br/>
<i><b>model calibration.</b></i> The 'process' whereby 'model' predictions are compared <br/>with field observations and/or experimental measurements from the <br/>'system' being modelled, and the 'model' is adjusted if necessary to achieve a <br/>best fit to the measured and/or observed data.<br/>
<b>!</b> This usage of the term is not universally accepted. The terms 'model validation'<br/>
and 'model verification' are more commonly used to describe related <i>processes<br/></i>in relation to 'models'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id85skos:definition "See 'container, waste'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id86skos:definition "See 'aircraft'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id87skos:definition "Any person, organization or government undertaking the carriage of <br/>
'radioactive material' by any means of 'transport'. The term includes both <i>carriers<br/></i>for hire or reward (known as common or contract 'carriers' in some countries) <br/>and 'carriers' on own account (known as private 'carriers' in some countries). <br/>(From Ref. [2].)<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id88skos:definition "<i><b>direct cause.</b></i> The 'latent weakness' that allows or causes the <i>observed cause<br/></i>of an 'initiating event' to happen, including the reasons for the <i>latent <br/>weakness</i>.<br/>
Corrective actions designed to address 'direct causes' are sometimes termed <br/>'repairs'.<br/>
<i><b>latent weakness.</b></i> An undetected degradation in an element of a <i>safety <br/>layer</i>.<br/>
Such a degradation could lead to that element failing to perform as expected <br/>if it were called upon to perform a function.<br/>
<i><b>observed cause.</b></i> The 'failure', action, omission or condition that directly <br/>leads to an 'initiating event'.<br/>
<i><b>root cause.</b></i> The fundamental cause of an 'initiating event', correction of <br/>which will prevent recurrence of the 'initiating event '(i.e. the 'root cause' is <br/>the 'failure' to detect and correct the relevant 'latent weakness(es) 'and the <br/>reasons for that 'failure'). <br/>
Corrective actions designed to address 'root causes' are sometimes termed <br/><i><b>remedies</b></i> (also 'remedial actions').<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id89skos:definition "An arrangement of interconnected 'components' within a 'system' that <br/>
initiates a single output. A 'channel' loses its identity where single output signals <br/>are combined with signals from other 'channels' (e.g. from a 'monitoring' <i>channel<br/></i>or a 'safety' actuation 'channel').<br/>
The above definition is specific to a particular area of 'nuclear safety'. The term <br/>'channel' is also used in its normal senses (and therefore normally without <br/>specific definition) in a variety of contexts.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id9skos:definition "Specified bounds on the value of a 'functional' 'indicator' or 'condition '<br/>
'indicator' used to assess the ability of a 'structure, system or component' to <br/>perform its 'design' function.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id90skos:definition "1. Determination of the nature and 'activity' of radionuclides present in a <br/>
specified place.<br/>
For example, determination of the radionuclides present in a 'bioassay' sample <br/>or in an area contaminated with 'radioactive material' (e.g. as a first step in <br/>planning 'remediation'). For the latter example, care should be taken to avoid <br/>confusion with the existing, and different, definition of the term <i>site <br/>characterization</i>.<br/>
2. Determination of the character of something.<br/>
This is the standard dictionary definition, and would not need to be included <br/>in an individual glossary. It is included here only to distinguish the normal <br/>usage from the more restricted usage indicated in (1).<br/>
<i><b>site characterization.</b></i> Detailed surface and subsurface investigations and <br/>'activities' at a site to determine the radiological conditions at the site or to <br/>
evaluate candidate 'disposal' sites to obtain information to determine the <br/>suitability of the site for a 'repository' and to evaluate the long term <br/>performance of a 'repository' at the site.<br/>
'Site characterization' is a stage in the 'siting' of a 'repository'; it follows <i>area <br/>survey</i> and precedes 'site confirmation'.<br/>'Site characterization' may also refer to the 'siting' 'process' for any other <br/>'authorized facility'. See also 'site evaluation', which includes <i>site characterization<br/></i>and is not specific to a 'repository' site, and 'area survey'.<br/>
<i><b>waste characterization.</b></i> Determination of the physical, chemical and <br/>radiological properties of the 'waste' to establish the need for further <br/>adjustment, 'treatment' or 'conditioning', or its suitability for further <br/>handling, 'processing', 'storage' or 'disposal'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id91skos:definition "See 'sorption'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id92skos:definition "In dosimetry (e.g. in tables of 'dose per unit intake' values), a 'child' is often <br/>assumed to be a 10 year old. If such an assumption is made, it should be <br/>clearly stated. See also 'infant' and 'reference individual'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id93skos:definition "See 'exposure situations'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id94skos:definition "See 'intake' (2).<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id95skos:definition "See 'exposure situations'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id96skos:definition "1. An external layer of material applied directly to another material to <br/>
provide protection in a chemically reactive environment (e.g. cladding over <br/>ferritic material to prevent corrosion).<br/>
2. Typically, the tube of material that houses the 'nuclear fuel' pellets and <br/>
provides the 'containment' of 'radioactive' species produced during fission.<br/>
It may also provide structural support.<br/>The cladding tube, together with the end cups or plugs, also typically provides <br/>structural support.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id97skos:definition "See 'remediation'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id98skos:definition "1. Removal of 'radioactive material' or 'radioactive' objects within <br/>
authorized' practices' from any further 'regulatory control' by the 'regulatory body'.<br/>
Removal from 'control' in this context refers to 'control' applied for <i>radiation <br/>protection</i> purposes.<br/>Conceptually, 'clearance' — freeing certain materials or objects in authorized<br/>'practices' from further 'control' — is closely linked to, but distinct from and not <br/>to be confused with, 'exemption' — determining that 'controls' do not need to be <br/>applied to certain 'sources' and 'practices'.<br/>Various terms are used in different States to describe this concept, e.g. ‘free <br/>release’.<br/>A number of issues relating to the concept of 'clearance' and its relationship to <br/>other concepts were resolved in Ref. [10].<br/>
2. The net effect of the biological 'processes' by which radionuclides are <br/>
removed from a tissue, organ or area of the body.<br/>
The <i><b>clearance rate</b></i> is the rate at which this occurs.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/iaeaSafetyGlossary/id99skos:definition "See 'level'.<br/>" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#Becquerelskos:definition "Measure of the rate of radioactive decay that corresponds to one atomic disintegration per second (1 Bq = 1 sec^-1). It is used as a measure of the amount of a radioactive material." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#BiomedicalTermskos:definition "Biomedical terms that include human physiology, medical conditions and treatments." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#BqperKgskos:definition "The unit of activity per mass of a radioactive material. Defined as Bq/kg." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#CommunicationToPublicTermskos:definition "Terms regarding communication to the public in the event of nuclear or radiological emergencies." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#FacilitiesTermskos:definition "Terms related to facilities used in nuclear and radiological emergencies." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#Grayskos:definition "Joules per kilogram (J/kg), the SI unit used for measuring the absorbed dose." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#NREmergencyManagementTermskos:definition "Terms about emergency procedures and especially nuclear and radiological emergency procedures." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#NuclearEngineeringTermskos:definition "Terms related to nuclear engineering fundamentals, physics, and the measurement of physical quantities." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#PreparednessTermskos:definition "Terms regarding preparedness for nuclear and radiological emergencies such as available resources and emergency response facilities" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#ResourcesTermskos:definition "Terms related to resources used in nuclear and radiological emergencies." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#Sievertskos:definition "The SI unit of equivalent dose and effective dose. 1 Sv = 1 J/kg." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#abbreviationskos:definition "Abbreviations, acronyms and other short forms." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#canonicalLabelskos:definition "The sub-property of skos:prefLabel that gives the most appropriate formal and unambiguous term for expressing a concept." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#centimetreskos:definition "centimetre (1E-2 m)" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#cpsskos:definition "counts per second" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#inContextAltLabelskos:definition "The sub-property of skos:altLabel that gives alternative forms for referring to a concept that might be in general ambiguous, but can be unambiguously and accurately used in the usual context of the concept. These are typically more general terms that are commonly understood with a restrcited meaning when found in the right context." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#informalLabelskos:definition "Informal terms often used by the public and/or to the mass media instead of the canonical term." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#manSievertskos:definition "Person-Sievert" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#microSievertskos:definition "1E-6 Sievert" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#micrometreskos:definition "micro metre (1E-6 m)" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#milliSievertskos:definition "1E-3 Sievert" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#obsoleteLabelskos:definition "Terms that should be understood but are no longer actively used." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo#obviousAbbreviationskos:definition "Established and well-understood abbreviations." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/CLORskos:definition "Central Laboratory for Radiological Protection in Poland" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/EEAEskos:definition "Ελληνική Επιτροπή Ατομικής Ενέργειας" (el)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/Euratomskos:definition "European Atomic Energy Community" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/FAOskos:definition "Food and Agriculture Organization of the United Nations" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/IACRNEskos:definition "Inter-Agency Committee on Radiological and Nuclear Emergencies" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/IAEAskos:definition "International Atomic Energy Agency" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/ICRPskos:definition "International Commission on Radiological Protection" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/IRSNskos:definition "French Institute for Radiological Protection and Nuclear Safety" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/NCRPskos:definition "U.S. National Council on Radiation Protection & Measurements" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/NCSRskos:definition "National Centre for Scientific Research "Demokritos"" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/NCSRskos:definition "Εθνικό Κέντρο Έρευνας Φυσικών Επιστημών "Δημόκριτος"" (el)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/NHSskos:definition "National Health Service" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/NIRSskos:definition "Japanese National Institute of Radiological Sciences" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/NRPAskos:definition "Norwegian Radiation Protection Authority" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/RANETskos:definition "Response Assistance Network of the IAEA" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/REMPANskos:definition "Radiation Emergency Medical Preparedness and Assistance Network" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/RelevantEntityskos:definition "Any entity relevant to nuclear technology." (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/ResearchOrganizationskos:definition "Nuclear Research Organization" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/SCKCENskos:definition "Belgian Nuclear Research Centre" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/STUKskos:definition "Radiation and Nuclear Safety Authority in Finland" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/WHOskos:definition "World Health Organization" (en)
-
http://rdf.iit.demokritos.gr/2014/nreo-entities/WMOskos:definition "World Meteorological Organization" (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/AMADskos:definition "In an aerosol containing radioactive particles with a range of sizes, fifty percent of the activity in the aerosol is associated with particles of aerodynamic diameter greater than the AMAD." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/Abrasionsskos:definition "Scraped area on the skin or on a mucous membrane, resulting from injury or irritation." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/AbsorbedDoseskos:definition "The amount of energy deposited by ionising radiation in a unit mass of tissue." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/AbsorptionTypeskos:definition "Materials are absorbed from the respiratory tract to body fluids with different rates. Chemical compounds are generally allocated to one of three default Absorption Types. These are Type F (i.e. fast, for very soluble materials), Type M (for moderately soluble materials), and Type S (i.e. slow, for relatively insoluble materials).
" (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/AbsorptionTypeFskos:definition "Fast absoption, for very soluble materials
" (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/AbsorptionTypeMskos:definition "Absorption for moderately soluble materials." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/AbsorptionTypeSskos:definition "Slow absorption, for relatively insoluble materials." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/AcuteRadiationSyndromeskos:definition "A set of characteristic signs and symptoms observed after whole body or large volume partial body exposure." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/AerodynamicDiameterskos:definition "The diameter of the unit density spherical particle that has the same settling velocity in air." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/Allogeneicskos:definition "Being genetically different although belonging to, or having been obtained from, the same species. This term is particularly used when talking about tissue grafts (e.g. skin graft or bone marrow transplantation)." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/Alopeciaskos:definition "Loss of hair" (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/AlphaRadiationskos:definition "A positively charged particle emitted from the nucleus of some radioactive atoms when they decay. It generally carries more energy than gamma or beta radiation and deposits that energy very quickly while passing through tissue, referred to as "high linear energy transfer" (high LET). Alpha particles cannot penetrate the outer layer of the skin and, therefore, do not cause damage when outside the body. However, they may be particularly damaging if alpha emitters are inhaled or ingested." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/AnalgesicTherapyskos:definition "Therapy addressed to control or eliminate pain." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/AntiEmeticTherapyskos:definition "Therapy addressed to prevent, stop, or relieve nausea and emesis (vomiting)." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/AnticipatoryStressskos:definition "Stress caused by concern over the future." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/Antiphlogisticskos:definition "An agent that counteracts inflammation." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/Aplasiaskos:definition "Failure to develop." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/Astheniaskos:definition "Weakness, lack/loss of energy and strength." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/AuthorisedPersonnelskos:definition "Assisting personnel such as police, fire fighters, medical personnel and drivers and crews of evacuation vehicles called upon to respond within the cordoned zones. In addition, radiation specialists, radiation protection officers and radiological assessors who may respond to emergencies, should be considered as authorised personnel." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/Autograftskos:definition "Tissue transplanted from one part of the body to another in the same individual." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/AutologousRecoveryskos:definition "Functional recovery from cells of the same individual." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/BetaRadiationskos:definition "A charged particle ejected from the nucleus of a decaying atom. It includes electrons (negatively charged) and positrons (positively charged). Beta particles penetrate the outer skin layer, are not stopped in tissue as quickly as alpha particles, and produce less damage per living cell (low LET)." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/Bioassayskos:definition "Procedures to evaluate internal contamination, including external monitoring for gamma emitting radionuclides, whole body counting and lung counting (in vivo analysis), and radiochemical analysis of excreta (e.g. urine) and other samples (in vitro analysis)." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/Biodosimetryskos:definition "Use of biological samples, usually taken from individuals who have been exposed to ionising radiation, to directly measure biological endpoints that can be correlated to absorbed radiation dose. Quantification of chromosome aberrations in peripheral lymphocytes (cytogenetic dosimetry) is the method of choice." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/Biokineticsskos:definition "In the field of radiation protection it refers to the kinetics of intake, distribution, retention and excretion of radionuclides in the body." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/Blisterskos:definition "Local swelling of the skin that contains watery fluid and is frequently caused by burning, infection, or irritation." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/BoneMarrowskos:definition "The soft, fatty, vascular tissue that fills most bone cavities and is the source of most blood cells." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/BrainOedimaskos:definition "An accumulation of fluids in the brain very often due to extravasation of fluid, plasma proteins, mainly albumin. Treatment can include diuretics and corticosteroids." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/BufferZoneskos:definition "Region near the border of a protected or controlled area established as a transition zone." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/CBRNskos:definition "Chemical, Biological, Radiological, Nuclear" (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/Cataractskos:definition "Opacity of the lens of the eye or its capsule (or both) that may result from injuries to the eye, ageing, exposure to great heat or radiation, or inherited factors." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/CategoryP1skos:definition "Trauma triage category for severely injured people who require immediate life saving intervention." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/CategoryP2skos:definition "Trauma triage category for people with less severe injuries (compared to Category P1) who will need hospital care, but whose transfer to a medical facility can be delayed for 10 – 12 hours." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/CategoryP3skos:definition "Trauma triage category for injured people who will require medical care, but may wait for a number of hours or be told to go home and return the next day (the "walking wounded")." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/ChemicalBurnsskos:definition "Tissue destruction caused by caustic agents, irritant gases, or other chemicals." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/ClonogenicAssayskos:definition "Experimental technique for studying the effectiveness of specific agents on the survival and proliferation of cells." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/CombinedInjuriesskos:definition "Radiation exposure in combination with burn, wound, trauma or infection." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/CommittedEffectiveDoseskos:definition "The time integral of the effective dose rate that will be received by an individual following an intake of radioactive material. It is the effective dose that an individual is committed to receive once an intake has taken place. The integration period is 50 years for adults, and from intake to 70 years of age for children." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/CommittedEffectiveDose50skos:definition "Committed Effective Dose to age 50 (Adults)" (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/CommittedEffectiveDose70skos:definition "E70: Committed Effective Dose to age 70 (Children)" (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/ConjunctivalHaemorrhageskos:definition "Haemorrhage that occurs beneath the conjunctiva, the transparent membrane covering the sclera." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/CordBloodskos:definition "Blood collected after the cord has been detached from a newborn baby, which may be utilised as a source of haematopoietic stem cells for transplantation." (en)
-
http://rdf.iit.demokritos.gr/2014/tmt/CrossContaminationskos:definition "Spreading of radioactive materials from one person, object or place to another." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/CutaneousRadiationSyndromeskos:definition "Injury to the skin and underlying tissues resulting from local exposure to a high external dose of ionising radiation." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Decorporationskos:definition "Process of treatment for persons with internally deposited radionuclides aimed at eliminating the material from the body and reducing the internal dose from exposure and hence, reducing the risk of health effects." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Dermatitisskos:definition "Skin inflammation." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/DeterministicHealthEffectskos:definition "Radiation induced health effect which occurs only above a given threshold level of radiation dose. The severity of the effect is greater for a higher dose. Examples include erythema (skin redness) and acute radiation syndrome. Not all deterministic effects are early effects." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/DoseRateskos:definition "The radiation dose delivered per unit of time." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/DoseReconstructionskos:definition "The process of estimating dose to people from radioactive contamination and/or exposure to an external source." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Dosemeterskos:definition "General term applied to devices designed to record personal exposure to ionising radiation. The dosemeter is the standard way of measuring personal exposure for the purposes of complying with statutory occupational dose limits." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Dosimetryskos:definition "Methods to measure or assess the radiation dose to people or objects exposed to ionising radiation, including reading of badges worn by potentially exposed individuals as well as bioassay (e.g. measurement of activity in the body through samples of urine, faeces, etc.)." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/EarlyEffectskos:definition "Radiation induced health effects that occur within some months after exposure." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/EffectiveDoseskos:definition "The sum of the equivalent doses to organs and tissues, weighted by the appropriate tissue weighting factors. These weighting factors represent the relative contribution of each organ or tissue to the total health detriment due to stochastic health effects resulting from uniform irradiation of the whole body. Effective dose provides a single quantity that can be used for radiation protection purposes to represent health detriment resulting from an intake of a radionuclide." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/ElectronicPersonalDosemeterskos:definition "EPDs are designed to provide real time information on dose and dose rate." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/EmergencyServicesskos:definition "Local public response organisations that are generally available and that perform emergency response functions. These may include law enforcement, fire fighters and rescue brigades, ambulance services and control teams for hazardous materials." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/EmergencyWorkerskos:definition "In the context of an incident involving ionising radiation, a worker who may be exposed in excess of occupational dose limits while performing actions to mitigate the consequences of an emergency for human health and safety, as well as severe consequences for property and the environment." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Emesisskos:definition "Vomiting" (en)
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http://rdf.iit.demokritos.gr/2014/tmt/EndarteritisObliteransskos:definition "Extreme degree of inflammation particularly affecting small arteries, accompanied by degeneration of the intima, leading to occlusion of the blood vessel." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/EndogenousMicrobialFloraskos:definition "Microorganisms found in various parts of the body such as skin, gut, mouth, upper respiratory tracts and genitals. Also called normal flora, this micro flora lives in harmony with the host. However, some types of flora are opportunists and seek to colonise when normal mechanisms of preventing disease are overcome (e.g. depression/ suppression of the immune responses)." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Endotheliumskos:definition "Layer of cells located at the interior surface of blood vessels, forming an interface between circulating blood and the rest of the vessel wall." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/EnvironmentalMonitoringskos:definition "The measurement of external dose rates in the environment, or of widespread contamination by radionuclides of environmental media." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Epidemicskos:definition "Occurrence of a disease in excess of its expected frequency." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/EquivalentDoseskos:definition "The absorbed dose averaged over a tissue or organ, with the contribution from each radiation type (alpha, beta, gamma, etc.) weighted by a radiation weighting factor that reflects the effectiveness of that radiation in causing stochastic health effects. This effectiveness is sometimes called the radiation quality. The unit of equivalent dose is the sievert (Sv)." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Erythemaskos:definition "Redness of skin and/or mucosa." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Excisionskos:definition "Surgical removal of any part or organ." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Excoriationskos:definition "Erosion or destruction of the skin by mechanical means." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/ExternalContaminationskos:definition "Radioactive material in the form of dust, solid particles, aerosols or liquid attached to a person’s skin or clothes." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/ExternalContaminationMonitoringskos:definition "Individual monitoring using measurements of the amount of radioactive material deposited on skin or clothing." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Fibrosisskos:definition "Development of excess fibrous connective tissue in an organ or tissue as a reparative or reactive process." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/FieldTriageskos:definition "All of those triage procedures that are carried out on the affected population outside of a hospital or other medical facility, either at the site of the incident or at a distance from it." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/FirstResponderskos:definition "The first members of emergency services to respond at the scene of an emergency." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/FollowUpskos:definition "In this context, subsequent contact with a person for the purpose of monitoring health status following exposure, diagnosis and/or treatment." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/GammaDoseRateskos:definition "The absorbed dose that would be received per unit time by human tissue placed in a defined gamma radiation field." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/GammaRadiationskos:definition "High energy photons emitted by the nuclei of decaying atoms. Gamma radiation can penetrate through several metres of solid material." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/GastroIntestinalUptakeFactorskos:definition "The fraction of material taken into the body by ingestion that is absorbed to body fluids as it passes through the gastro-intestinal tract. Chemical compounds are assigned a default value of f1 between 0 and 1." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/GraftRejectionskos:definition "In haematology, the expression is used to describe the situation when bone marrow infused during a transplant is rejected by the donor." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/GraftVsHostskos:definition "A serious complication of bone marrow transplantation where there is a reaction of donated bone marrow against the patient’s own tissues." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Granulocytopeniaskos:definition "Reduced number of blood granulocytes, namely neutrophils, eosinophils, and basophils." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/HMStemCellsskos:definition "Multipotent cells that can differentiate either in vivo or in vitro into a variety of cell types such as myocytes (muscle cells), adipocytes, osteoblasts and hondrocytes." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Haematopoiesisskos:definition "Formation of blood cellular components, which are derived from haematopoietic stem cells." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/HaematopoieticFailureskos:definition "Bone marrow aplasia." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/HaematopoieticStemCellskos:definition "Multipotent cells with the ability to become several different types of cell in the blood system." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/HealthDetrimentskos:definition "A measure of the harm that would eventually be experienced by an exposed group and its descendants as a result of the group’s exposure to a source of ionising radiation." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/HealthSurveillanceskos:definition "Tracking and forecasting of any health event or health determinant through the collection of data, the integration, analysis and interpretation of those data into surveillance products (e.g. reports, advisories, alerts, and/or warnings), and the dissemination of those surveillance products to relevant public bodies. Surveillance products are produced for a specific public health purpose or policy objective." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/HereditaryEffectskos:definition "Radiation induced health effects that occur in a descendant of the exposed person (the less precise term "genetic effects" is also used). They are related to changes in germinal cells." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Histocompatibilityskos:definition "Property of having the same, or mostly the same, alleles of a set of genes called the major histocompatibility complex (also called in humans HLA). These genes are expressed in most tissues as antigens to which the immune system makes antibodies. If the body is exposed to foreign antigens, e.g. by getting a tissue graft, it attacks the foreign material unless it is histocompatible." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Hyperkeratosisskos:definition "Thickening of the skin following production of an excess of proteins." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Hypotensionskos:definition "Abnormally low blood pressure." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Immunosuppressionskos:definition "Act or effect that reduces the activation or efficacy of the immune system. Deliberately induced immunosuppression may be done to prevent the body from rejecting an organ transplant, to treat Graft Versus Host Disease after bone marrow transplant, or for the treatment of auto-immune diseases." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/IndividualMonitoringskos:definition "Monitoring using measurements of quantities of radioactive material in or on the body of the individual, or measurements made by equipment worn by individual workers. It includes the assessment of radiation doses to the individual from the results of such measurements." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/InpatientCareskos:definition "Medical services provided to a person admitted for overnight stay in a hospital." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/InternalContaminationskos:definition "Radionuclides incorporated within the body as a result of inhalation, ingestion, direct absorption through open wounds or intact skin and mucosa." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/InternalContaminationMonitoringskos:definition "Individual monitoring using measurements of the amount of radioactive material in the body. Measurements may be direct (e.g. measurement of activity in the lungs using external detectors) or indirect (e.g. measurement of activity excreted in samples of urine)." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/InternalDosimetryskos:definition "Methods to assess the dose that a person is committed to receive as a result of an intake of a given amount of radioactive material." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/IonisingRadiationskos:definition "For the purpose of radiation protection, radiation capable of producing ion pairs in biological material." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Isodoseskos:definition "A radiation dose of equal intensity to more than one body area. An isodose chart is a diagram of depth dose measurement at various positions within a radiation beam in which points of equal dose throughout the beam are joined to give isodose lines." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Lacerationskos:definition "A tear in the skin which results from a mechanical injury." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/LateEffectskos:definition "Radiation induced health effects that occur years after exposure." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/LymphocyteSubpopulationsskos:definition "Morphologically identical types of lymphocytes that can be distinguished by their cell surface antigens. Different subpopulations of lymphocytes play essential functions in human humoral or cell mediated immunity (i.e. immunity mediated by cells or by secreted antibodies)." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Lymphocytosisskos:definition "Abnormal increase in the number or proportion of lymphocytes in the blood." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Lymphopeniaskos:definition "Abnormal decrease in the number or proportion of lymphocytes in the blood." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/METREPOLskos:definition "Medical Treatment Protocols for radiation accident victims" (en)
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http://rdf.iit.demokritos.gr/2014/tmt/MagneticResonanceImagingskos:definition "Magnetic Resonance Imaging" (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Monitoringskos:definition "The measurement of radiation dose or contamination, for reasons related to the assessment or control of exposure to radiation or radioactive material, and the interpretation of the results." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Morbidityskos:definition "In medicine this term can refer either to the state of being ill or to the degree or severity of a disease. In epidemiology, this term is also used to refer to the prevalence or incidence of a disease. The prevalence is the total number of cases, in a particular population at a particular point in time. The incidence is the number of new cases in a particular population during a particular time interval. The term morbidity rate can refer either to the incidence rate or to the prevalence rate of a disease (to compare, see also mortality)." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Mortalityskos:definition "A measure of the number of deaths in a given population. Mortality rate is the number of people dying during a given time interval, divided by the total number of people in the population." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/MultipleOrganDysfunctionskos:definition "Altered organ function involving two or more organ systems which may occur in acutely ill patients such that homeostasis cannot be maintained without intervention." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/MultipleOrganFailureskos:definition "A progressive condition usually characterised by combined failure of several organs such as the lungs, liver, kidney, along with some clotting mechanisms." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Myelosuppressionskos:definition "Condition in which bone marrow activity is decreased, resulting in fewer red blood cells, white blood cells, and platelets." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/NSAIDskos:definition "Non-Steroid Anti-Inflammatory" (en)
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http://rdf.iit.demokritos.gr/2014/tmt/NationalFocalPointskos:definition "National Focal Point" (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Neovascularisationskos:definition "Proliferation of new blood vessels." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/NeutropenicPatientskos:definition "Patient with neutropenia, which is defined specifically as a decrease in the number of circulating neutrophils. See also Granulocytopenia." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/OCPskos:definition "Location established in the Red Zone on the Safety Perimeter to provide rapid access to the incident location for emergency personnel and where rapid initial screening measurements can be performed." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/OccupancyTimeskos:definition "Time spent by an individual at a given location." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Oedimaskos:definition "Swelling of any organ or tissue due to accumulation of excess lymph fluid, without an increase of the number of cells in the affected tissue." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/OmentumFlapskos:definition "Omentum or epiplon is a large fold of peritoneum. In reconstructive plastic surgery, a segment of omentum, with its supplying blood vessels, may be transplanted as a free flap to a distant area." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Onycholisisskos:definition "Separation of the nail plate from the nail bed." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/OutpatientCareskos:definition "Medical services that are provided without the need for an overnight stay in a hospital, e.g. through an ambulatory care clinic or emergency department." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Pancytopeniaskos:definition "Medical condition in which there is a reduction in the number of red and white blood cells, as well as platelets." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Pemphigusskos:definition "Term that includes a group of rare autoimmune skin disorders characterised by the development of blisters in the outer layer of the skin (epidermis) and mucous membranes.
" (en)
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http://rdf.iit.demokritos.gr/2014/tmt/PersonalProtectiveEquipmentskos:definition "Specialised safety clothing or equipment worn for protection against health and safety hazards, especially in the work environment. Personal protective equipment may be designed to protect many parts of the body, i.e. eyes, head, face, hands, feet, and ears. Such equipment must be used when the existing risks cannot be sufficiently limited by other means." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/PersonalRadiationDetectorskos:definition "Personal Radiation Detector" (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Petechiaeskos:definition "Small red or purple spots on the body, caused by a minor bleeding from broken capillary blood vessels." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/PostTraumaticStressDisorderskos:definition "Anxiety disorder that can develop after exposure to a highly stressful event or ordeal. Severe and ongoing emotional reaction to an extreme psychological trauma." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/ProliferationResponseTestsskos:definition "In immunology, group of tests to evaluate the functional status of lymphocytes." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/PublicHealthskos:definition "Science and art of preventing disease, prolonging life and promoting good health." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Punctureskos:definition "Incision of tissues for injection of medication or for other diagnostic or therapeutic procedures." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/RadiationEmergencyMedicineskos:definition "Emergency medicine related to the management of health effects resulting from radiation exposure of individuals and populations." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/RadiationProtectionskos:definition "The protection of people from the effects of exposure to ionising radiation, and the means for achieving this." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/RadiationSourceskos:definition "Anything that may cause radiation exposure, such as by emitting ionising radiation or by releasing radioactive material, and can be treated as a single entity for protection and safety purposes." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/RadioactiveContaminationskos:definition "Unwanted radioactive material inside the body or on the body surfaces (internal or external contamination, respectively). Contaminated persons are continually exposed to radiation until the contamination is removed." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/RadioactiveMaterialskos:definition "Material emitting ionising radiation and designated in national law or by a regulatory body as being subject to regulatory control because of its radioactivity." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/RadioactiveSourceskos:definition "Radioactive material that is permanently sealed in a capsule or closely bonded in a solid form and which is not exempt from regulatory control. This also includes any radioactive material released if the radioactive source is leaking or broken." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/RadioactiveWasteskos:definition "Waste that contains, or is contaminated with, radionuclides at concentrations or activities greater than clearance levels established by the regulatory body." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Radiodermatitisskos:definition "Dermatitis due to exposure to ionising radiation." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/RadiologicalDispersalDeviceskos:definition "Any device that causes the purposeful dispersion of radioactive material without a nuclear detonation." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/RadiologicalExposureDeviceskos:definition "Device designed to cause external exposure to ionising radiation." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/RadiologicalTriageskos:definition "Triage based on a consideration of actual or potential effects on health arising from exposure to ionising radiation." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/RedZoneskos:definition "The potentially hazardous area immediately surrounding an incident location." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/RelativeBiologicalEffectivenessskos:definition "A relative measure of the effectiveness of different radiation types at inducing a specified health effect, expressed as the inverse ratio of the absorbed doses of two different radiation types that would produce the same degree of a defined health effect (the “degree” being probability for stochastic health effects, and severity for deterministic health effects)." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/ResidualHaematopoiesisskos:definition "In the context of acute radiation syndrome, it refers to the functional activity remaining after bone marrow radiation damage." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/ReverseIsolationskos:definition "A system designed to protect patients from getting an infection caused by germs - bacteria, viruses or fungi - that may be in the environment or carried by staff and visitors." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/SACPskos:definition "A gateway on the Safety Perimeter providing controlled rapid access between the Red Zone and Yellow Zone." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/SafetyPerimeterskos:definition "The boundary of the Red Zone." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/SecurityPerimeterskos:definition "The boundary of the Yellow Zone." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/SomaticEffectskos:definition "Radiation induced health effects that occur in the exposed person." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/SourceMonitoringskos:definition "The measurement of the activity of radioactive material or of external dose rates in the localised area around a source." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/StabWoundskos:definition "A wound where the depth of injury is greater than the length and may come into contact with vital organs in the chest and abdomen." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/StochasticHealthEffectskos:definition "Radiation induced health effects where the probability of occurrence is greater for higher radiation doses, but where the severity of the effects (if they occur) is independent of dose. They generally occur without a threshold level of dose and they may be somatic (i.e. they occur in the exposed person e.g. cancer) or hereditary effects (i.e. they occur in the descendant of the exposed person)." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Stockpilesskos:definition "In the context of public health, it refers to medical supplies stored, carefully accrued and maintained, so they can be made rapidly available when needed." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/StrategicCommandskos:definition "The Strategic Command is in overall charge of the response to the incident, but is not present at the scene. The Strategic Command is likely to be headed by a senior member of the Security Forces (e.g. Police) or a senior member of local government." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/TCPskos:definition "The location in the Yellow Zone from which on-site management and coordination takes place." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/TICskos:definition "The TIC is in overall charge of all personnel operating at the site of the incident. It is likely to be led by the most senior member of the First Responder teams attending. The TIC reports to Strategic Command." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/TMTskos:definition "Triage, Monitoring, Treatment" (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Telangiectasiaskos:definition "Small dilated superficial blood vessels giving rise to tenderness, pain or discomfort when an affected area is touched." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Tendernessskos:definition "Pain or discomfort when an affected area is touched." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/ThermalBurnsskos:definition "Injuries to tissues caused by heat, characterised by degree, based on the severity of the tissue damage." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Thrombocytopeniaskos:definition "Presence of sub-normal numbers of platelets in blood.
" (en)
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http://rdf.iit.demokritos.gr/2014/tmt/TransdermalAbsorptionskos:definition "Absorption of a substance through the skin. It occurs through a slow process of diffusion, driven by the gradient between the high concentration in the delivery system and the zero concentration prevailing in the skin." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Traumaskos:definition "Any injury, whether physically or emotionally inflicted. Physical injury trauma may be caused by violent or disruptive action, or by the introduction into the body of a toxic substance. Psychological injury trauma can result from a severe emotional shock." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/TraumaTriageskos:definition "Triage based on degree of physical injury." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/Triageskos:definition "The use of simple procedures for rapidly sorting people into groups based (a) on their degree of physical injury and (b) on actual or potential effects on health, and the allocation of care to these people so as to expedite treatment and maximise the effective use of resources." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/UnrelatedDonorskos:definition "Allogeneic (as opposed to autologous) hematopoietic cell transplantation remains a challenge due to the risk of graft rejection in the HLA mismatched settings. In the absence of matched sibling donors, alternative donors such as unrelated and/or partially matched family sources may be options." (en)
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http://rdf.iit.demokritos.gr/2014/tmt/WorriedWellskos:definition "In emergencies, this term refers to people requesting assistance because they think they may have been exposed to a chemical, physical or biological agent, but who have not actually been exposed." (en)
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http://www.w3.org/2004/02/skos/core#Collectionskos:definition "A meaningful collection of concepts." (en)
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http://www.w3.org/2004/02/skos/core#Conceptskos:definition "An idea or notion; a unit of thought." (en)
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http://www.w3.org/2004/02/skos/core#ConceptSchemeskos:definition "A set of concepts, optionally including statements about semantic relationships between those concepts." (en)
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http://www.w3.org/2004/02/skos/core#OrderedCollectionskos:definition "An ordered collection of concepts, where both the grouping and the ordering are meaningful." (en)
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http://www.w3.org/2004/02/skos/core#altLabelskos:definition "An alternative lexical label for a resource." (en)
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http://www.w3.org/2004/02/skos/core#broadMatchskos:definition "skos:broadMatch is used to state a hierarchical mapping link between two conceptual resources in different concept schemes." (en)
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http://www.w3.org/2004/02/skos/core#broaderskos:definition "Relates a concept to a concept that is more general in meaning." (en)
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http://www.w3.org/2004/02/skos/core#broaderTransitiveskos:definition "skos:broaderTransitive is a transitive superproperty of skos:broader." ()
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http://www.w3.org/2004/02/skos/core#changeNoteskos:definition "A note about a modification to a concept." (en)
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http://www.w3.org/2004/02/skos/core#closeMatchskos:definition "skos:closeMatch is used to link two concepts that are sufficiently similar that they can be used interchangeably in some information retrieval applications. In order to avoid the possibility of "compound errors" when combining mappings across more than two concept schemes, skos:closeMatch is not declared to be a transitive property." (en)
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http://www.w3.org/2004/02/skos/core#editorialNoteskos:definition "A note for an editor, translator or maintainer of the vocabulary." (en)
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http://www.w3.org/2004/02/skos/core#exactMatchskos:definition "skos:exactMatch is used to link two concepts, indicating a high degree of confidence that the concepts can be used interchangeably across a wide range of information retrieval applications. skos:exactMatch is a transitive property, and is a sub-property of skos:closeMatch." (en)
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http://www.w3.org/2004/02/skos/core#exampleskos:definition "An example of the use of a concept." (en)
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http://www.w3.org/2004/02/skos/core#hasTopConceptskos:definition "Relates, by convention, a concept scheme to a concept which is topmost in the broader/narrower concept hierarchies for that scheme, providing an entry point to these hierarchies." (en)
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http://www.w3.org/2004/02/skos/core#hiddenLabelskos:definition "A lexical label for a resource that should be hidden when generating visual displays of the resource, but should still be accessible to free text search operations." (en)
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http://www.w3.org/2004/02/skos/core#historyNoteskos:definition "A note about the past state/use/meaning of a concept." (en)
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http://www.w3.org/2004/02/skos/core#inSchemeskos:definition "Relates a resource (for example a concept) to a concept scheme in which it is included." (en)
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http://www.w3.org/2004/02/skos/core#mappingRelationskos:definition "Relates two concepts coming, by convention, from different schemes, and that have comparable meanings" (en)
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http://www.w3.org/2004/02/skos/core#memberskos:definition "Relates a collection to one of its members." (en)
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http://www.w3.org/2004/02/skos/core#memberListskos:definition "Relates an ordered collection to the RDF list containing its members." (en)
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http://www.w3.org/2004/02/skos/core#narrowMatchskos:definition "skos:narrowMatch is used to state a hierarchical mapping link between two conceptual resources in different concept schemes." (en)
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http://www.w3.org/2004/02/skos/core#narrowerskos:definition "Relates a concept to a concept that is more specific in meaning." (en)
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http://www.w3.org/2004/02/skos/core#narrowerTransitiveskos:definition "skos:narrowerTransitive is a transitive superproperty of skos:narrower." ()
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http://www.w3.org/2004/02/skos/core#notationskos:definition "A notation, also known as classification code, is a string of characters such as "T58.5" or "303.4833" used to uniquely identify a concept within the scope of a given concept scheme." (en)
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http://www.w3.org/2004/02/skos/core#noteskos:definition "A general note, for any purpose." (en)
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http://www.w3.org/2004/02/skos/core#prefLabelskos:definition "The preferred lexical label for a resource, in a given language." (en)
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http://www.w3.org/2004/02/skos/core#relatedskos:definition "Relates a concept to a concept with which there is an associative semantic relationship." (en)
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http://www.w3.org/2004/02/skos/core#relatedMatchskos:definition "skos:relatedMatch is used to state an associative mapping link between two conceptual resources in different concept schemes." (en)
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http://www.w3.org/2004/02/skos/core#scopeNoteskos:definition "A note that helps to clarify the meaning and/or the use of a concept." (en)
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http://www.w3.org/2004/02/skos/core#semanticRelationskos:definition "Links a concept to a concept related by meaning." (en)
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http://www.w3.org/2004/02/skos/core#topConceptOfskos:definition "Relates a concept to the concept scheme that it is a top level concept of." (en)
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skos:definition SubPropertyOf skos:note