ISO 12749-2:2013
(Main)Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 2: Radiological protection
Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 2: Radiological protection
ISO 12749-2:2013 lists unambiguous terms and definitions related to radiological protection concepts in the subject field of nuclear energy. It is intended to facilitate communication and promote common understanding.
Énergie nucléaire, technologies nucléaires et protection radiologique — Vocabulaire — Partie 2: Protection radiologique
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Standards Content (Sample)
INTERNATIONAL ISO
STANDARD 12749-2
First edition
2013-09-15
Nuclear energy, nuclear technologies,
and radiological protection —
Vocabulary —
Part 2:
Radiological protection
Énergie nucléaire, technologies nucléaires et protection
radiologique — Vocabulaire —
Partie 2: Protection radiologique
Reference number
ISO 12749-2:2013(E)
©
ISO 2013
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ISO 12749-2:2013(E)
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ii © ISO 2013 – All rights reserved
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ISO 12749-2:2013(E)
Contents Page
Foreword .iv
0. Introduction .v
Scope 1
1 General terms related to radiological protection. 1
2 Terms related to biological effect . 4
3 Terms related to radiological exposure. 5
4 Terms related to radiological monitoring . 9
5 Terms related to measurement .12
6 Terms related to technical aspects .14
7 Terms related to regulation .16
Annex A (informative) Methodology used in the development of the vocabulary .20
Annex B (informative) Alphabetical index .30
Bibliography .33
© ISO 2013 – All rights reserved iii
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ISO 12749-2:2013(E)
Foreword
ISO (the International Organization for Standardization) is a worldwide federation of national standards
bodies (ISO member bodies). The work of preparing International Standards is normally carried out
through ISO technical committees. Each member body interested in a subject for which a technical
committee has been established has the right to be represented on that committee. International
organizations, governmental and non-governmental, in liaison with ISO, also take part in the work.
ISO collaborates closely with the International Electrotechnical Commission (IEC) on all matters of
electrotechnical standardization.
The procedures used to develop this document and those intended for its further maintenance are
described in the ISO/IEC Directives, Part 1. In particular the different approval criteria needed for the
different types of ISO documents should be noted. This document was drafted in accordance with the
editorial rules of the ISO/IEC Directives, Part 2. www.iso.org/directives
Attention is drawn to the possibility that some of the elements of this document may be the subject of
patent rights. ISO shall not be held responsible for identifying any or all such patent rights. Details of
any patent rights identified during the development of the document will be in the Introduction and/or
on the ISO list of patent declarations received. www.iso.org/patents
Any trade name used in this document is information given for the convenience of users and does not
constitute an endorsement.
The committee responsible for this document is ISO/TC 85, Nuclear energy, nuclear technologies, and
radiological protection.
ISO 12749 consists of the following parts, under the general title Nuclear energy, nuclear technologies,
and radiological protection — Vocabulary.
— Part 2: Radiological protection
The following parts are under preparation:
— Part 3: Nuclear fuel cycle
iv © ISO 2013 – All rights reserved
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ISO 12749-2:2013(E)
0. Introduction
0.1 General
This part of ISO 12749 provides terms and definitions for general nuclear energy concepts dealing with
radiological protection and other related concepts, such as means of protection for human health and
environment, measurement methods and instruments, and the prevision or direct determination of the
effect of ionizing radiations on the body. Terminological data are taken from International Standards
developed by the SC 2 and other technically validated documents such as the IAEA Glossary, IAEA BSS,
ICRP, ICRU 60, ICRU 51, VIM, and BIPM.
Unambiguous communication of radiological protection concepts is crucial, taking into account
the relevant implications that may arise from misunderstandings with regard to equipment and
materials involved in the standards dealing with this subject. The market of radiological protection is a
heterogeneous one because it comprises equipment designed, built, and operated along the safe practices
defined by radiological protection specialists. This market also includes nuclear reactors, nuclear fuel
cycle, and instruments to monitor both personnel and facilities and sites. In view of the foregoing, a
large number of people having different levels of scientific and technical knowledge are involved; thus,
there can be widely divergent understandings and assumptions about concepts. The results are poor
communication, high risk of accidents, and duplication of effort as different groups are going to define
concepts according to their perspectives.
Conceptual arrangement of terms and definitions is based on concepts systems that show
corresponding relationships among radiological protection concepts. Such arrangement provides users
with a structured view of this special subdomain within the nuclear energy sector and will facilitate
common understanding of radiological protection concepts. Besides, concepts systems and conceptual
arrangement of terminological data will be helpful to any kind of user because it will promote clear,
accurate, and useful communication. At the end of this part of ISO 12749, an alphabetical index shows
the terms followed by their corresponding notation.
0.2 Structure of the vocabulary
The terminology entries are presented in the conceptual order of the English preferred terms. Both a
systematic index and an alphabetical index are included. The structure of each entry is in accordance
with ISO 10241-1:2011.
All the terms included in this part of ISO 12749 deal exclusively with radiation protection. When selecting
terms and definitions, special care has been taken to include the terms that need to be defined, that is
to say, either because the definitions are essential to the correct understanding of the corresponding
concepts or because some specific ambiguities need to be addressed.
The notes appended to certain definitions offer clarification or examples to facilitate understanding of
the concepts described. In certain cases, miscellaneous information is also included, for example, the
units in which a quantity is normally measured, recommended parameter values, references, etc.
According to the title, the vocabulary deals with concepts belonging to the general nuclear energy subject
field within which concepts in the radiological protection sub-subject field are taken into account.
© ISO 2013 – All rights reserved v
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INTERNATIONAL STANDARD ISO 12749-2:2013(E)
Nuclear energy, nuclear technologies, and radiological
protection — Vocabulary —
Part 2:
Radiological protection
Scope
This part of ISO 12749 lists unambiguous terms and definitions related to radiological protection
concepts in the subject field of nuclear energy. It is intended to facilitate communication and promote
common understanding.
1 General terms related to radiological protection
1.1
radiological protection
radiation protection
protection of people and the environment from the harmful effects of exposure to ionizing radiation and
the means for achieving such protection
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007
Edition, modified — By adding “and the environment”.]
1.1.1
radiation source
anything (apparatus, substance, installation) that may cause radiation exposure, such as by emitting
ionization radiation or releasing radioactive substances or materials
[SOURCE: ISO 14152:2001]
1.1.1.1
radioactivity
stochastic process whereby nuclei undergo spontaneous disintegration, usually accompanied by the
emission of subatomic particles, or photons
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007
Edition, modified — By deleting “random” between “spontaneous” and “disintegration”.]
1.1.1.1.1
radioactive material
material of which one or more constituents exhibit radioactivity (1.1.1.1)
Note 1 to entry: For special purposes such as regulation, this term may be restricted to radioactive material
(1.1.1.1.1) with an activity or a specific activity greater than a specified value.
[SOURCE: ISO 921:1997]
1.1.1.1.1.1
radioactive contamination
radioactive substances on surfaces, or within solids, liquids, or gases (including the human body), where
their presence is unintended or undesirable, or the process giving rise to their presence in such places
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007 Edition]
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ISO 12749-2:2013(E)
1.1.1.1.1.1.1
surface contamination
radioactive material (1.1.1.1.1) deposited on surfaces of facilities (floor surface, work bench tops,
machines, etc.), equipment, or personnel
1.1.2
equilibrium equivalent radon concentration
concentration of radon in air, in equilibrium with its short-lived decay products, which would have the
same potential alpha energy concentration as the existing non-equilibrium mixture
[SOURCE: UNSCEAR 2006, Appendix E]
1.1.2.1
equilibrium factor
ratio of the equilibrium equivalent concentration of radon to the actual radon concentration
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007 Edition]
1.1.3
justification
process of determining for a planned exposure situation whether a practice is, overall, beneficial or
for an emergency exposure situation or an existing exposure situation whether a proposed protective
action or remedial action is likely, overall, to be beneficial
[SOURCE: Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards -
Interim Edition IAEA Safety Standards Series GSR Part 3, 2011]
1.1.4
optimization of protection
process of determining what level of protection and safety makes exposures, and the probability and
magnitude of potential exposures, as low as reasonably achievable, economic and societal factors being
taken into account
[SOURCE: ICRP 103, modified — By adding “as low as reasonably achievable, economic and societal
factors being taken into account” at the end.]
1.1.5
dose
measure of the energy deposited by radiation in a target
[SOURCE: Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards -
Interim Edition IAEA Safety Standards Series GSR Part 3, 2011]
Note 1 to entry: Abbreviation for any of the existing dose quantities such as absorbed dose, effective dose, or
equivalent dose.
Note 2 to entry: If unqualified, the dose quantity should be indicated by the context.
1.1.6
dose limit
limit on equivalent dose (3.3.2) and/or on effective dose (3.3.4) that is applied for exposure to individuals
in order to prevent the occurrence of radiation-induced deterministic effects or to limit the probability
of radiation-related stochastic effects to an acceptable level
[SOURCE: National Council on Radiation Protection and Measurements USA, Glossary, modified — By
changing “radiation dose” to “equivalent dose” and adding “and/or on effective dose”.]
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ISO 12749-2:2013(E)
1.1.6.1
partial-body dose
equivalent dose (3.3.2) to tissue, organs, or parts of the body
Note 1 to entry: Identified by the name of the part of the particular tissue, organ, or body, e.g. bone marrow dose,
skin dose, hand dose, testes dose, or dose to the lens of the eyes.
−1
Note 2 to entry: The unit of equivalent dose (3.3.2) is joule per kilogram (J·kg ) and its special name is sievert (Sv).
[SOURCE: ISO 15382:2002, modified — By stating the examples in Note 1 and adding Note 2.]
1.1.6.2
annual dose
dose from external exposure (3.2) in a year plus the committed dose (3.1.2) from intakes of
radionuclides in that year
[SOURCE: IAEA Basic Safety Standards, March 2011]
1.1.6.3
total dose
dose from external exposure (3.2) in a given period plus the committed dose (3.1.2) from intakes of
radionuclides in that same period
[SOURCE: IAEA – Radiation Protection and Safety of Radiation Sources: International Basic Safety
Standards - Interim Edition IAEA Safety Standards Series GSR Part 3, 2011]
1.1.7
dose constraint
prospective and source-related value of individual dose or risk that is used in planned exposure situations
(3.4.1) as a parameter for the optimization of protection (1.1.4) and safety for the source, and that serves
as a boundary in defining the range of options in optimization
[SOURCE: IAEA – Radiation Protection and Safety of Radiation Sources: International Basic Safety
Standards - Interim Edition IAEA Safety Standards Series GSR Part 3, 2011]
1.1.8
derived limit
limit on a measurable quantity set, on the basis of a model, such that compliance with the derived limit
may be assumed to ensure compliance with a primary limit
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007 Edition]
1.1.9
derived air concentration
DAC
derived limit (1.1.8) on the activity concentration in air of a specified radionuclide, calculated such that
reference individual, breathing air with constant contamination at the concentration while performing
light physical activity for a working year, would receive an intake corresponding to the annual limit on
intake (1.1.9.1) for the radionuclide in question
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007
Edition, modified — By replacing “Reference Man” with “reference individual”.]
Note 1 to entry: The parameter values recommended by the International Commission on Radiological Protection
3
for calculating DACs are a breathing rate of 1,2 m /h and a working year of 2 000 h.
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ISO 12749-2:2013(E)
1.1.9.1
annual limit on intake
ALI
intake (3.1.1) by inhalation or ingestion or through the skin of a given radionuclide in a year by reference
individual which would result in a committed dose (3.1.2) equal to the relevant dose limit (1.1.6)
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007
Edition, modified — By changing “reference man” to “reference individual”.]
Note 1 to entry: The annual limit on intake is expressed in units of activity.
2 Terms related to biological effect
2.1
threshold dose
level of dose (1.1.5) above which a deterministic effect occurs
2.1.1
deterministic effect
tissue reaction
biological effect of radiation for which a threshold dose (2.1) exists above
which the severity of the effect is greater for a higher dose
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007
Edition, modified — By deleting “limit of” and the notes.]
[SOURCE: ICRP 103:2007]
2.1.1.1
acute radiation syndrome or sickness
ARS
acute illness caused by irradiation of the entire body (or most of the body) by a high dose of penetrating
radiation in a very short period of time (usually a matter of minutes)
[SOURCE: ISO 21243:2008]
2.2
linear non-threshold model
LNT model
dose-response model which is based on the assumption that, in the low dose range, radiation doses greater
than zero will increase the risk of excess cancer and/or heritable disease in a simple proportionate manner
[SOURCE: ICRP 103:2007]
2.2.1
stochastic effect
radiation-induced health effect, whose probability of occurrence is greater for a higher radiation dose
and the severity of which (if it occurs) is independent of dose
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007
Edition, modified — By changing “the probability of occurrence of which” to “whose probability of
occurrence”.]
Note 1 to entry: Stochastic effects may be somatic effects or hereditary effects and generally occur without a
threshold level of dose. Examples include solid cancers and leukaemia.
2.2.1.1
somatic effect
radiation-induced health effect that occurs in the exposed person
Note 1 to entry: Somatic effect includes effects occurring after birth that are attributable to exposure in uterus.
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ISO 12749-2:2013(E)
Note 2 to entry: Deterministic effects are normally also somatic effects.
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007
Edition, modified — By splitting the note in two and by deleting “stochastic effects may be somatic
effects or hereditary effects” in Note 2.]
2.2.1.2
hereditary effect
radiation-induced health effect that occurs in a descendant of the exposed person
Note 1 to entry: The less precise term ‘genetic effect’ is also used, but hereditary effect is preferred.
Note 2 to entry: Hereditary effects are usually stochastic effects.
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007
Edition, modified — By omitting Note 3.]
2.2.2
risk coefficient
lifetime risk or radiation detriment assumed to result from exposure to unit equivalent dose (3.3.2) or
effective dose (3.3.4)
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007 Edition]
3 Terms related to radiological exposure
3.1
internal exposure
exposure to radiation from a source inside the body
[SOURCE: Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards -
Interim Edition IAEA Safety Standards Series GSR Part 3, 2011]
3.1.1
intake
activity of a radionuclide taken into the body in a given time period or as a result of a given event
[SOURCE: ISO 20553:2006]
3.1.1.1
dose coefficient
dose per unit intake of a radioactive substance
Note 1 to entry: Sometimes, it is also used to describe other coefficients linking quantities or concentrations of
activity to doses or dose rates, such as the external dose rate at a specified distance above a surface with a deposit
of a specified activity per unit area of a specified radionuclide.
[SOURCE: ICRP 103, modified — By splitting the wording into a definition and a note.]
3.1.1.2
human alimentary tract model
HATM
model that describes the processes that are involved when a radioactive material (1.1.1.1.1) is incorporated
by human ingestion
[SOURCE: ICRP 66, modified — By changing “ingestion by children and adults” to “human ingestion”.]
Note 1 to entry: HATM provides age-dependent parameter for the tract region, and associated transit times for
the movement of materials through this region.
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ISO 12749-2:2013(E)
3.1.1.3
human respiratory tract model
HRTM
model that describes the processes that are involved when a radioactive material (1.1.1.1.1) is incorporated
by human inhalation
[SOURCE: ICRP 66, modified to be consistent with the definition of human alimentary tract model]
3.1.1.4
retention fraction
fraction of an intake present in the body or in a tissue, organ, or region of the body after a given time has
elapsed since the intake occurred
[SOURCE: ICRP 68]
3.1.1.5
excretion fraction
fraction of an intake excreted per day after a given time has elapsed since the intake occurred
[SOURCE: ICRP 68]
3.1.1.6
specific absorbed fraction
fraction of energy that is emitted as a specified radiation type in a source region, S, that is absorbed in
1 kg of a target tissue, T
[SOURCE: ICRP 103:2007]
3.1.1.7
clearance class
lung absorption class
classification used to distinguish between the different rates at which the inhaled radionuclides are
transferred from the respiratory tract to the blood
3.1.2
committed dose
lifetime dose expected to result from an intake (3.3.1)
[SOURCE: Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards -
Interim Edition IAEA Safety Standards Series GSR Part 3, 2011]
3.2
external exposure
exposure to radiation from a source outside the body
[SOURCE: IAEA – Radiation Protection and Safety of Radiation Sources: International Basic Safety
Standards - Interim Edition IAEA Safety Standards Series GSR Part 3, 2011]
3.3
organ dose
mean absorbed dose (4.1.6.7)D in a specified tissue or organ, T, of the human body, given by:
T
1 ε
T
D == ∫=Ddm
T m
T
m m
T T
where m is the mass of the tissue or organ, D is the absorbed dose (4.1.6.7) in the mass element dm, and
T
ε is the total energy imparted
T
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007 Edition]
6 © ISO 2013 – All rights reserved
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ISO 12749-2:2013(E)
3.3.1
radiation weighting factor
W
R
number by which the absorbed dose (4.1.6.7) in a tissue or organ is multiplied to reflect the relative
biological effectiveness of the radiation in inducing stochastic effects (2.2.1) at low doses, the result
being the equivalent dose (3.3.2)
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007 Edition]
3.3.2
equivalent dose
H
T
the quantity H defined as:
T,R
Hw= D
TR,,RT R
where D is the absorbed dose (4.1.6.7) delivered by radiation type, R, averaged over a tissue or organ,
T,R
T, and W is the radiation weighting factor for radiation type, R. When the radiation field is composed of
R
different radiation types with different values of W , the equivalent dose is:
R
Hw= D
TR∑ TR,
R
−1
Note 1 to entry: The unit of equivalent dose is joule per kilogram (J·kg ) and its special name is sievert (Sv).
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007
Edition, modified — By deleting the last part of Note 1 and Notes 2 and 3.]
3.3.3
tissue weighting factor
W
T
multiplier of the equivalent dose (3.3.2) to an organ or tissue used for radiation protection purposes to
account for the different sensitivities of different organs and tissues to the induction of stochastic effects
(2.2.1) of radiation
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007 Edition]
3.3.4
effective dose
E
sum of the equivalent dose (3.3.2) in tissue or organ, W , multiplied by the appropriate tissue weighting
T
factor, T, given by the expression Ew= H where H is the equivalent dose (3.3.2) in tissue or organ,
T
∑ TT
T, each multiplied by the appropriate tissue weighting factor for tissue, T
[SOURCE: ICRP 103:2007, modified — By rewording “result of the summation of the equivalent doses in
tissues or organs, each multiplied by the appropriate tissue weighting factor”.]
−1
Note 1 to entry: The unit of effective dose is joule per kilogram (J·kg ) and its special name is sievert (Sv).
3.4.1
planned exposure situation
situation arising from the planned operation of a source radiation or from a planned action that results
in an exposure from a source radiation
[SOURCE: Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards -
Interim Edition IAEA Safety Standards Series GSR Part 3, 2011, modified — By changing “activity” to
“action” and adding “radiation” after “source”.]
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ISO 12749-2:2013(E)
3.4.1.1
use factor
fraction of the workload during which the useful beam is pointed toward the area in question
[SOURCE: IEC IEV 50 Radiology and radiological physics/Radiation protection: methods and monitoring]
3.4.1.2
occupancy factor
T
factor by which the workload should be multiplied in order to correct for the degree or type of occupancy
of the area in question
[SOURCE: IEC IEV 50 Radiology and radiological physics/Radiation protection: methods and monitoring]
3.4.1.3
occupational exposure
exposure of workers incurred in the course of their work
[SOURCE: Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards -
Interim Edition IAEA Safety Standards Series GSR Part 3, 2011]
3.4.1.4
medical exposure
exposure incurred by patients for the purposes of medical or dental diagnosis or treatment; by careers
and comforters; and by volunteers subject to exposure as part of a programme of biomedical research
3.4.1.5
public exposure
exposure incurred by members of the public due to sources in planned exposure situations (3.4.1) and
existing exposure situations, excluding any occupational or medical exposure and the normal local
natural background radiations
[SOURCE: ICRP 103:2007]
3.4.2
existing exposure situation
situation of exposure which already exists when a decision on the need for control needs to be taken
[SOURCE: Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards -
Interim Edition IAEA Safety Standards Series GSR Part 3, 2011]
Note 1 to entry: Examples are exposure to background radiation and exposure to residual radioactive material
(1.1.1.1.1) from a nuclear or radiological emergency after the emergency exposure situation (3.4.3) has been
declared ended.
3.4.2.1
potential exposure
exposure that is not expected to be delivered with certainty but that may result from an accident at
a source, an event, or sequence of events of a probabilistic nature, including equipment failures and
operating errors
[SOURCE: ICRP 103:2007]
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ISO 12749-2:2013(E)
3.4.3
emergency exposure situation
situation of exposure where exposure at an elevated level is inevitable due to unexpected events or
needs of important action
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007
Edition, modified — By adding “where exposure at an elevated level is inevitable due to unexpected
events or needs of important action”.]
Note 1 to entry: This may include unplanned exposures resulting directly from the emergency and planned
exposures to persons undertaking actions to mitigate the consequences of the emergency.
Note 2 to entry: Emergency exposure may be occupational exposure or public exposure.
3.4.3.1
reference level
in an emergency exposure situation (3.4.3) or an existing exposure situation (3.4.2), level of dose (1.1.5),
risk, or activity concentration above which it is not appropriate to plan to allow exposures to occur and
below which optimization of protection (1.1.4) and safety would continue to be implemented
[SOURCE: IAEA – Radiation Protection and Safety of Radiation Sources: International Basic Safety
Standards - Interim Edition IAEA Safety Standards Series GSR Part 3, 2011]
3.4.4
averted dose
dose prevented by the application of a countermeasure or set of countermeasures, i.e. the difference
between the projected dose if the countermeasure(s) had not been applied and the actual projected dose
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007 Edition]
4 Terms related to radiological monitoring
4.1
radiological monitoring
radiation monitoring
monitoring
measurement of dose or contamination for reasons related to the assessment or control of exposure to
radiation or radioactive substances, and the interpretation of the results
[SOURCE: IAEA Safety Glossary Terminology Used in Nuclear Safety and Radiation Protection – 2007 Edition]
4.1
...
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