ISO 12749-2:2022

INTERNATIONAL ISO
STANDARD 12749-2
Second edition
2022-08
Nuclear energy, nuclear technologies,
and radiological protection —
Vocabulary —
Part 2:
Radiological protection
Énergie nucléaire, technologies nucléaires et protection
radiologique — Vocabulaire —
Partie 2: Radioprotection
Reference number
ISO 12749-2:2022(E)
© ISO 2022

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ISO 12749-2:2022(E)
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© ISO 2022
All rights reserved. Unless otherwise specified, or required in the context of its implementation, no part of this publication may
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Published in Switzerland
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ISO 12749-2:2022(E)
Contents Page
Foreword .iv
Introduction .v
1 Scope . 1
2 Normative references . 1
3 Terms and definitions . 1
3.1 General terms related to radiological protection . 1
3.2 General terms related to biological effect . 6
3.3 Terms related to radiation exposure . 8
3.4 Terms related to measurement and radiological monitoring .13
3.5 Terms related to technical aspects. 25
3.6 Terms related to regulation . 27
3.7 Terms related to emergency .29
Annex A (informative) Methodology used in the development of the vocabulary .32
Bibliography .43
Index .46
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ISO 12749-2:2022(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 (see 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 (see 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.
For an explanation of the voluntary nature of standards, the meaning of ISO specific terms and
expressions related to conformity assessment, as well as information about ISO's adherence to
the World Trade Organization (WTO) principles in the Technical Barriers to Trade (TBT), see
www.iso.org/iso/foreword.html.
This document was prepared by Technical Committee ISO/TC 85, Nuclear energy, nuclear technologies,
and radiological protection.
This second edition cancels and replaces the first edition (ISO 12749-2:2013), which has been technically
revised.
The main changes are as follows:
— Merging of the headings “Terms related to radiological monitoring” and “Terms related to
measurement”.
— Addition of the heading “Terms related to emergency”.
A list of all parts in the ISO 12749 series can be found on the ISO website.
Any feedback or questions on this document should be directed to the user’s national standards body. A
complete listing of these bodies can be found at www.iso.org/members.html.
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ISO 12749-2:2022(E)
Introduction
This document will provide terms and definitions for general nuclear energy concepts dealing with
radiological protection and other related concepts. These concepts include protection for human health
and the environment; radiation measurement methods and instruments; and the prevision or direct
determination of the effect of ionizing radiation on the body.
Terminological data are taken from ISO standards developed and revised by ISO/TC 85/SC 2 and other
technically validated documents such as the IAEA Basic Safety Standards, ISO/IEC 80000-10, ICRP,
ICRU 51, ICRU 85a, 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 the radiological protection specialists. This market also includes nuclear reactors,
nuclear fuel cycle, cosmic radiation, scientific research industrial applications, nuclear medicine
and radiotherapy, and instruments to monitor both personnel and facilities and sites. In view of the
foregoing, and the large number of people involved who have different levels of scientific and technical
knowledge, 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. In Annex A there is a detailed explanation
of this subject. Such arrangement provides users with a structured view of this special sub domain
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
document an alphabetical index shows the terms followed by their corresponding notation.
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INTERNATIONAL STANDARD ISO 12749-2:2022(E)
Nuclear energy, nuclear technologies, and radiological
protection — Vocabulary —
Part 2:
Radiological protection
1 Scope
This document defines terms and definitions related to radiological protection concepts in the subject
field of nuclear energy, nuclear technology and the different nuclear applications. It is intended to
facilitate communication and promote common understanding.
2 Normative references
There are no normative references in this document.
3 Terms and definitions
For the purposes of this document, the following terms and definitions apply.
ISO and IEC maintain terminological databases for use in standardization at the following addresses:
— ISO Online browsing platform: available at https:// www .iso .org/ obp
— IEC Electropedia: available at https:// www .electropedia .org/
3.1 General terms related to radiological protection
3.1.1
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 while allowing its beneficial uses
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278, modified — “and the
environment” and “while allowing its beneficial uses” was added and the demonstrative pronoun “that”
was replaced with “such protection”.]
Note 1 to entry: People include workers, patients and members of the public.
Note 2 to entry: Environment includes biota, waters, lands, and air.
3.1.2
radiation source
source
apparatus, substance or installation, that can cause radiation exposure (3.3.1), by emitting ionizing
radiation or releasing radioactive substances or materials
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ISO 12749-2:2022(E)
3.1.3
radioactivity
stochastic process whereby nuclei undergo spontaneous random disintegration, usually accompanied
by the emission of subatomic particles, or photons
[SOURCE: ISO 12749-1:2020, 3.1.1, modified — “random” was added in the definition.]
3.1.4
radioactive material
material designated in national law or by a regulatory body as being subject to regulatory control
because of its radioactivity (3.1.3)
Note 1 to entry: This is the ‘regulatory’ meaning of radioactive, and should not be confused with the ‘scientific’
meaning of radioactive.
Note 2 to entry: The term radioactive substance is also used to indicate that the ‘scientific’ meaning of radioactive
is intended, rather than the ‘regulatory” meaning of radioactive suggested by the term radioactive material.
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278]
Note 3 to entry: Whenever the term "radioactive substance" is mentioned in any definition or note to entry
throughout this document, it covers the concept defined in 3.1.4.
3.1.5
radioactive contamination
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. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278, modified — The
parenthesis was deleted and replaced with commas.]
3.1.6
airborne radioactive substance
radioactive substance dispersed in the air in the form of dusts, fumes, particulates, mists, vapours, or
gases
[SOURCE: ISO 16639:2017, 3.4]
3.1.7
derived air concentration
DAC
derived limit (3.1.15) on the activity concentration in air of a specified radionuclide, calculated such
that the reference individual, breathing air with constant contamination at the DAC with the breathing
behavior of a reference worker for a working year, would receive an intake (3.3.4) corresponding to the
annual intake for the radionuclide in question
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.
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278]
3.1.8
air contamination area
area accessible to individuals where the measured or calculated radioactivity (3.1.3) concentrations of
an airborne radioactive substance (3.1.6) exceeds or is likely to exceed the applicable criteria
[SOURCE: ISO 16639:2017, 3.5, modified — Addition of “or calculated”, “activity” was changed to
“radioactivity” and deletion of “national” from “to exceed the applicable national criteria”.]
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ISO 12749-2:2022(E)
3.1.9
decontamination
complete or partial removal of radioactive contamination (3.1.5) by a deliberate physical, chemical or
biological process
Note 1 to entry: It is preferred that radioactive decontamination does not significantly change the characteristics
of the surface.
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278, modified — “the” was
deleted from the definition and “radioactive” was added in the definition and the Note 1 to entry.]
3.1.10
justification
process of determining for an emergency exposure situation (3.3.26) or an existing exposure situation
(3.3.27) whether a proposed protective action or remedial action is likely to be beneficial, whether the
expected benefits to individuals and to society from introducing or continuing the protective action or
remedial action outweigh the cost of such action and any harm or damage caused by the action
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278, modified — “overall”
and “including the reduction in radiation detriment” were deleted.]
3.1.11
optimization (of protection and safety)
process of determining what level of protection and safety would result in the magnitude of individual
doses, the number of individuals, workers and members of the public, subject to exposure and the
likelihood of exposure being as low as reasonably achievable, economic and social factors being taken
into account (ALARA)
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278]
Note 1 to entry: For medical exposures (3.3.29) of patients, the optimization of protection and safety is the
management of the radiation dose to the patient commensurate with the medical purpose.
3.1.12
dose limit
value of the effective dose (3.1.24) or the equivalent dose (3.1.22) to individuals from planned exposure
situations (3.3.21), or doses (3.1.16) to biota, that shall not be exceeded
[SOURCE: 2007 Recommendations of the International Commission on Radiological Protection.
ICRP Publication 103. Ann. ICRP 37 (2-4)]
3.1.13
dose constraint
prospective and source related value of individual dose (3.1.16) that is used in planned exposure
situations (3.3.21) as a parameter for the optimization of protection and safety (3.1.11) for the source,
and that serves as a boundary in defining the range of options in optimization
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278]
3.1.14
annual limit on intake
ALI
intake (3.3.4) 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 (3.1.17) equal to the relevant dose limit (3.1.12)
Note 1 to entry: The annual limit on intake is expressed in units of activity.
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278]
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ISO 12749-2:2022(E)
3.1.15
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. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278]
3.1.16
dose
measure of the energy deposited by radiation in a target
[SOURCE: IAEA. IAEA safety glossary, 2018 Edition. Vienna: IAEA, 2019. p. 278]
Note 1 to entry: When unspecified, dose refers to quantity of absorbed dose (3.1.20), measured in gray (1 Gy = 1 J/
kg).
Note 2 to entry: Depending upon the context in which it is used, the generic term dose may also refer to equivalent
dose (3.1.22), effective dose (3.1.24) or other dose-related quantities.
[SOURCE: ISO 12749-1:2020, 3.3.6]
3.1.17
committed dose
lifetime dose (3.1.16) expected to result from an intake (3.3.4)
[SOURCE: IAEA. Radiation protection and safety of radiation sources: international basic safety
Standards. IAEA Safety Standards Series No, GSR Part 3. Vienna: IAEA, 2014. p. 471]
Note 1 to entry: For radiological protection (3.1.1) calculational purposes, lifetime is typically taken to be 50 years
for adults and the time to the age of 70 years for intakes by children. (That is, for intakes by children, 70 years
minus the age in years: so, for example 60 years for 10 years old child).
3.1.18
committed equivalent dose
H (τ)
T
quantity H (τ), defined as:
T
t +τ
0
HH()τ = ()t dt
TT
∫
t
0
where t is the time of intake (3.3.4), H (t) is the equivalent dose (3.1.22) rate at time t in tissue or organ
0 T
T and τ is the integration time elapsed after an intake of radioactive substances
Note 1 to entry: Where τ is not specified, it is taken to be 50 years for adults and the time to the age of 70 years
for intakes by children. (That is, for intakes by children, 70 years minus the age in years: so, for example 60 years
for a 10 years old child).
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278]
3.1.19
committed effective dose
E(τ)
quantity E(τ), defined as:
Ew()ττ= T ()
∑ T T
T
where H (τ) is the committed equivalent dose (3.1.18) to tissue or organ T over the integration time τ
T
elapsed after an intake (3.3.4) of radioactive substances and w is the tissue weighting factor (3.1.23) for
T
tissue or organ T.
Note 1 to entry: Where τ is not specified, it will be taken to be 50 years for adults and the time to the age of
70 years for intakes by children.
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ISO 12749-2:2022(E)
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278]
3.1.20
absorbed dose
D
differential quotient of ε with respect to m, where ε is the mean energy imparted by ionizing radiation
to matter of mass m:
dε
D=
dm
[SOURCE: ISO 80000-10:2019, 10.81.1]
Note 1 to entry: The gray is a special name for joule J/kg and is to be used as the coherent SI unit for absorbed
dose.
3.1.21
radiation weighting factor
w
R
dimensionless factor by which the organ or tissue absorbed dose (3.1.20) is multiplied to reflect the
higher biological effectiveness of high-LET (3.1.25) radiations compared with low-LET radiations. It is
used to derive the equivalent dose (3.1.22) from the absorbed dose averaged over a tissue or organ
Note 1 to entry: The radiation weighting factor is used to derive the equivalent dose from the absorbed dose
averaged over a tissue or organ.
[SOURCE: 2007 Recommendations of the International Commission on Radiological Protection.
ICRP Publication 103. Ann. ICRP 37 (2-4) modified — The definition was split into a definition and a
Note to entry.]
3.1.22
equivalent dose
quantity H defined as: Hw= D where D is the absorbed dose (3.1.20) delivered by
TR, TR,,RT R TR,
radiation type R averaged over a tissue or organ T and w is the radiation weighting factor (3.1.21) for
R
radiation type R
Note 1 to entry: When the radiation field is composed of different radiation types with different values of w the
R
equivalent dose is:
Hw= D
∑
TR T,R
R
Note 2 to entry: The unit of equivalent dose is J/kg and its special name is sievert (Sv).
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278. modified — The
definition was split into a definition and two Notes to entry.]
3.1.23
tissue weighting factor
w
T
multiplier of the equivalent dose (3.1.22) to an organ or tissue used for radiological protection (3.1.1)
purposes to account for the different sensitivities of different organs or tissues to the induction of
stochastic effects (3.2.5) of radiation
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278]
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ISO 12749-2:2022(E)
3.1.24
effective dose
E
tissue-weighted sum of the equivalent doses (3.1.22) in all specified tissues and organs of the body, given
by the expression:
ED=oww r=EHw
∑∑ ∑
T RT,R T T
T R T
where H or w D is the equivalent dose in a tissue or organ, T, and w is the tissue weighting factor
T R T,R T
(3.1.23)
Note 1 to entry: The unit for the effective dose is J/kg, and its special name is sievert (Sv).
Note 2 to entry: In order to evaluate the effective dose different anthropomorphic reference models are used;
they can be adapted to sex and age.
[SOURCE: 2007 Recommendations of the International Commission on Radiological Protection.
ICRP Publication 103. Ann. ICRP 37 (2-4)]
3.1.25
linear energy transfer
LET
quotient of the mean energy, dE , lost by the charged particles due to electronic interactions in
Δ
traversing a distance, dl, minus the mean sum of the kinetic energies in excess of Δ of all the electrons
released by charged particles and dl:
dE
Δ
L =
Δ
dl
[SOURCE: ISO 80000-10:2019, 10.85]
3.1.26
relative biological effectiveness
RBE
ratio of a dose of a low-LET (3.1.25) reference radiation to a dose of the radiation considered that gives
an identical biological effect (3.2.1)
[SOURCE: 2007 Recommendations of the International Commission on Radiological Protection.
ICRP Publication 103. Ann. ICRP 37 (2-4)]
Note 1 to entry: The most used reference radiation is 250 keV x-rays.
3.2 General terms related to biological effect
3.2.1
biological effect
effect of ionizing radiation in living cells
EXAMPLE Erythema, damage to the haemopoietic system, and acute radiation syndrome.
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278]
3.2.2
deterministic effect
tissue reaction
radiation induced health effect for which generally a threshold level of dose (3.1.16) exists above which
the severity of the effect is greater for a higher dose
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278]
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ISO 12749-2:2022(E)
3.2.3
acute radiation syndrome
acute radiation sickness
ARS
acute illness caused by irradiation of the entire body (or most of the body) by a high dose (3.1.16) of
penetrating radiation in a very short period of time (usually a matter of minutes)
Note 1 to entry: The required conditions for Acute Radiation Syndrome (ARS) are:
— The radiation dose is large (i.e., greater than 0,7 Gy).
— The dose is usually from an external exposure.
— The radiation is penetrating.
— The entire body (or a significant portion of it) has received the dose.
[SOURCE: Brochure for Physicians, Acute Radiation Syndrome, Centers for Disease Control and
Prevention, https:// www .cdc .gov/ nceh/ radiation/ emergencies/ pdf/ ars .pdf]
Note 2 to entry: With the assumption of the linear-non-threshold dose response for stochastic radiation effects
(LNT model (3.2.8)) in the low dose range (< 100 mSv) and, under the conditions of the described concept of
calculation, effective dose (3.1.24) is an additive quantity. At higher radiation doses, when tissue reactions
(deterministic effects (3.2.2)) can occur, the absorbed doses (3.1.20) in organs and tissues have to be used for risk
evaluation.
[SOURCE: 2007 Recommendations of the International Commission on Radiological Protection.
ICRP Publication 103. Ann. ICRP 37 (2-4)]
3.2.4
threshold dose
dose estimated to result in only 1 % incidence of tissue reactions
[SOURCE: 2007 Recommendations of the International Commission on Radiological Protection.
ICRP Publication 103. Ann. ICRP 37 (2-4)]
3.2.5
stochastic effect
radiation induced health effect, whose probability of occurrence is greater for a higher radiation dose
(3.1.16) and which severity, if it occurs, is independent of dose
Note 1 to entry: Stochastic effects may be somatic effects (3.2.9) or hereditary effects (3.2.10), and generally occur
without a threshold level of dose. Examples include solid cancers and haematologic cancers (leukaemia and
lymphoma).
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278, modified — “the
probability of occurrence of which” was replaced with “whose probability of occurrence” and ”leukemia”
was replaced with “haematologic cancers”.]
3.2.6
risk coefficient
lifetime risk or radiation detriment (3.2.7) assumed to result from exposure to unit equivalent dose
(3.1.22) or effective dose (3.1.24)
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278]
3.2.7
radiation detriment
total harm that would eventually be incurred by a group that is subject to exposure and by its
descendants as a result of the group’s exposure to radiation from a source
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p.278]
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ISO 12749-2:2022(E)
3.2.8
linear-non-threshold model
LNT model
dose-response model, which is based on the assumption that, in the low dose range, radiation doses
(3.1.16) greater than zero will increase the risk of excess cancer and/or heritable disease in a simple
proportionate manner
[SOURCE: 2007 Recommendations of the International Commission on Radiological Protection.
ICRP Publication 103. Ann. ICRP 37 (2-4)]
Note 1 to entry: Low doses (below about 100 mSv) and low dose rates.
3.2.9
somatic effect
radiation induced health effect that occurs in the exposed individual
Note 1 to entry: Somatic effect includes effects occurring after birth that are attributable to exposure in uterus.
Note 2 to entry: Deterministic effects (3.2.2) are normally also somatic effects.
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278, modified — The note
was split in two and “stochastic effects may be somatic effects or hereditary effects” was deleted in the
second one.]
3.2.10
hereditary effect
radiation induced health effect that occurs in a descendant of the exposed individual
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 (3.2.5).
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278]
3.3 Terms related to radiation exposure
3.3.1
radiation exposure
state or condition of being subject to ionizing radiation
Note 1 to entry: Exposure to ionizing radiation can be broadly divided into categories of exposure according to
the status of the individual.
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278, modified — “irradiation”
was replaced with “ionizing radiation”.]
3.3.2
internal exposure
exposure to radiation from a source within the body
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278]
3.3.3
specific absorbed fraction
SAF
fraction of energy of that emitted as a specified radiation type in a source region, S, that is absorbed per
unit mass of a target tissue, T
[SOURCE: 2007 Recommendations of the International Commission on Radiological Protection.
ICRP Publication 103. Ann. ICRP 37 (2-4) modified — “that is absorbed in 1 kg” was replaced with “that
is absorbed per unit mass”.]
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ISO 12749-2:2022(E)
3.3.4
intake
act or process of taking radionuclides into the body by inhalation or ingestion or through the skin
[SOURCE: IAEA. IAEA safety glossary: 2018 edition. Vienna: IAEA, 2019. p. 278 modified — The phrase
“by the operator” was deleted.]
EXAMPLE Intake by injection of a radiopharmaceutical, via a wound, or any other possible exposure
pathway.
3.3.5
absorption
transfer of material to blood regardless of mechanism, generally applied to dissociation of particles and
uptake into blood of soluble substances and material dissociated from particles
[SOURCE: ISO 16638-1:2015, 3.1, modified — “movement” was changed to “transfer”, “which generally”
with “generally” and “the uptake” with “uptake”.]
3.3.6
human alimentary tract model
HATM
biokinetic model for describing the movement of ingested materials through the human alimentary
tract
[SOURC
...