ISO 20043-1:2021

INTERNATIONAL ISO
STANDARD 20043-1
First edition
2021-01
Measurement of radioactivity in
the environment — Guidelines for
effective dose assessment using
environmental monitoring data —
Part 1:
Planned and existing exposure
situation
Mesurage de la radioactivité dans l'environnement — Lignes
directrices pour l’évaluation de la dose efficace à l’aide de données de
surveillance environnementale —
Partie 1: Situation d'exposition existante et planifiée
Reference number
ISO 20043-1:2021(E)
©
ISO 2021

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ISO 20043-1:2021(E)

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© ISO 2021
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ISO 20043-1:2021(E)

Contents Page
Foreword .iv
Introduction .v
1 Scope . 1
2 Normative references . 1
3 Terms and definitions . 2
4 Symbols . 5
5 Principle . 5
6 Assessing and monitoring human exposure. 8
7 Environmental monitoring program .10
7.1 General .10
7.2 Planning process .11
7.2.1 Selection of the sampling strategy .11
7.2.2 Description of the sampling plan .11
7.3 Sampling process .11
7.3.1 Collection of samples .11
7.3.2 Preparation of the sorted sample .12
7.4 Laboratory process .12
7.4.1 Handling of the laboratory sample .12
7.4.2 Preparation of the test sample .12
8 Environmental monitoring to assess external exposure .12
8.1 General .12
8.2 Direct measurement of the external dose .13
8.3 Indirect assessment of the external dose .14
8.3.1 External exposure from contaminated soil .14
8.3.2 External exposure from contaminated air .15
9 Environmental monitoring to assess internal exposure .15
9.1 General .15
9.2 Inhalation.16
9.3 Ingestion .17
9.3.1 General.17
9.3.2 Ingestion of water .17
9.3.3 Ingestion of agricultural products .18
10 Radioactivity measurement .18
10.1 General .18
10.2 Soil .18
10.3 Water .19
10.4 Food stuffs .20
11 Variability and uncertainty .21
12 Quality assurance and quality control program .21
Annex A (informative) Example of sampling procedures for environmental and food matrices .23
Annex B (informative) Example of sample preparation methods for environmental and
food matrices .24
Annex C (informative) Investigation to identify the cause of increase of ambient dose and
activity concentration of environmental samples above their background levels.25
Bibliography .26
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ISO 20043-1:2021(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 on 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 the following URL: Foreword - Supplementary
information
This document was prepared by Technical Committee ISO/TC 85, Nuclear energy, nuclear technologies,
and radiological protection, Subcommittee SC 2, Radiological protection.
A list of all the parts in the ISO 20043 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 20043-1:2021(E)

Introduction
Everyone is exposed to natural radiation. The natural sources of radiation are cosmic rays and naturally
occurring radioactive substances existing in the Earth itself and inside the human body. Human
activities involving the use of radiation and radioactive substances (NORM) cause radiation exposure in
addition to the natural exposure. Some of those activities, such as the mining and use of ores containing
naturally-occurring radioactive substances and the production of energy by burning coal that contains
such substances, simply enhance the exposure from natural radiation sources. Nuclear installations
use radioactive materials and produce radioactive effluent and waste during operation and on their
decommissioning. The use of radioactive materials in industry, agriculture and research is expanding
around the globe.
All these human activities generally also give rise to radiation exposures that are only a small fraction
of the global average level of natural exposure. The medical use of radiation is the largest and a growing
man-made source of radiation exposure in developed countries. It includes diagnostic radiology,
radiotherapy, nuclear medicine and interventional radiology.
Radiation exposure also occurs as a result of occupational activities. It is incurred by workers in
industry, medicine and research using radiation or radioactive substances, as well as by passengers
and crew during air travel and for astronauts. The average level of occupational exposures is generally
[1]
similar to the global average level of natural radiation exposure .
As the uses of radiation increase, so do the potential health risks and the public’s concerns increase.
Thus, all these exposures are regularly assessed in order to
a) improve the understanding of global levels and temporal trends of public and worker exposure,
b) evaluate the components of exposure so as to provide a measure of their relative importance, and
c) identify emerging issues that may warrant more attention and scrutiny. While doses to workers
are usually directly measured, doses to the public are usually assessed by indirect methods
using radioactivity measurement results performed on various sources: waste, effluent and/or
environmental samples.
To ensure that the data obtained from radioactivity monitoring programs support their intended use,
it is essential in the dose assessment process that stakeholders (the operators, the regulatory bodies,
the local information committee and associations, etc.) agree on appropriate data quality objectives,
methods and procedures for: the sampling, handling, transport, storage and preparation of test
samples; the test method; and for calculating measurement uncertainty. An assessment of the overall
measurement uncertainty also needs to be carried out systematically. As reliable, comparable and ‘fit
for purpose’ data are an essential requirement for any public health decision based on radioactivity
measurements, international standards of tested and validated radionuclide test methods are an
important tool for the production of such measurement results. The application of standards serves
also to guaranty comparability over time of the test results and between different testing laboratories.
Laboratories apply them to demonstrate their technical competences and to complete proficiency tests
successfully during interlaboratory comparisons, two prerequisites to obtain national accreditation.
Today, over a hundred international standards, prepared by Technical Committees of the International
Organization for Standardization, including those produced by ISO/TC 85 working groups, and the
International Electrotechnical Commission, are available for measuring radionuclides in different
matrices by testing laboratories.
Generic standards help laboratories to manage the measurement process and specific standards
describing test methods are used specifically by those in charge of radioactivity measurement. These
later cover test methods for:
40 3 14
— Natural radionuclides, including K, H, C and those originating from the thorium and uranium
226 228 234 238 220 222 210
decay series, in particular Ra, Ra, U, U, Rn, Rn, Pb, which can be found in every
material from natural sources or can be released from technological processes involving naturally
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ISO 20043-1:2021(E)

occurring radioactive materials (e.g. the mining and processing of mineral sands or phosphate
fertilizer production and use), and
— Man-made radionuclides, such as transuranium elements (americium, plutonium, neptunium, and
3 14 90
curium), H, C, Sr and gamma emitting radionuclides found in waste, liquid and gases effluent
and in environmental matrices (air, soil, water, biota) as a result of authorized releases into the
environment and of fallout resulting from the explosion in the atmosphere of nuclear devices and
3
accidents, such as those that occurred in Chernobyl and Fukushima. Radionuclides, such as H and
14
C occur both naturally and as by-products of the operation of nuclear reactors.
[2]
The ICRP recognises three types of exposure situations that are intended to cover the entire range of
exposure situations: planned, emergency and existing exposure situations. Planned exposure situations
involve the planned introduction and operation of sources (previously categorised as practices).
Emergency exposure situations are situations requiring prompt action in order to avoid or to reduce
adverse consequences. Existing exposure situations are exposure situations that already exist when
a decision on control is taken, such as those caused by enhanced natural background radiation (e.g.
exposure to radon in existing buildings).
The fraction of the background dose rate to man from environmental radiation, mainly gamma
radiation, is very variable and depends on factors such as the radioactivity of the local rock and soil, the
nature of building materials and the construction of buildings in which people live and work.
This document sets out principles and guidance for the radiological characterisation of the environment
needed for checking the results of
— prospective assessment of dose to the public arising from exposure to ionizing radiation which
may arise from planned discharges to the atmosphere and to the aquatic environment or following
remediation action;
— retrospective assessment for dose that may be made for discharges or disposals that were not initially
covered by an authorization/permit delivered by a national regulatory body (e.g. contaminated land
or dose associated with accidental releases of radionuclides into the environment).
This document is one of a set of generic ISO Standards on measurement of radioactivity.
Example of dose assessment in different exposure situations, modified from Reference [3]
Type of assessment
Situation
Prospective Retrospective
Planned Determining compliance with Estimating dose to the public from past
the relevant dose constraint (dose limit operations
or regulatory requirements). A prospective
assessment includes the exposures expected
to occur in normal operation.
Existing Future prolonged exposures (e.g. after Past exposures (e.g. occupancy
remediation) of contaminated lands)
Emergency Emergency planning (operational Actual impacts after emergency
intervention level)
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INTERNATIONAL STANDARD ISO 20043-1:2021(E)
Measurement of radioactivity in the environment —
Guidelines for effective dose assessment using
environmental monitoring data —
Part 1:
Planned and existing exposure situation
1 Scope
These international guidelines are based on the assumption that monitoring of environmental
components (atmosphere, water, soil and biota) as well as food quality ensure the protection of
[2][4][5][6][7][8]
human health . The guidelines constitute a basis for the setting of national regulations
and standards, inter alia, for monitoring air, water and food in support of public health, specifically to
protect the public from ionizing radiation.
This document provides
— guidance to collect data needed for the assessment of human exposure to radionuclides naturally
present or discharged by anthropogenic activities in the different environmental compartments
(atmosphere, waters, soils, biological components) and food;
— guidance on the environmental characterization needed for the prospective and/or retrospective
dose assessment methods of public exposure;
— guidance for staff in nuclear installations responsible for the preparation of radiological assessments
in support of permit or authorization applications and national authorities’ officers in charge of
the assessment of doses to the public for the purposes of determining gaseous or liquid effluent
radioactive discharge authorizations;
— information for the public on the parameters used to conduct a dose assessment for any exposure
situations to a representative person/population. It is important that the dose assessment process
be transparent, and that assumptions are clearly understood by stakeholders who can participate
in, for example, the selection of habits of the representative person to be considered.
Generic mathematical models used for the assessment of radiological human exposure are presented
to identify the parameters to monitor, in order to select, from the set of measurement results, the "best
estimates" of these parameter values. More complex models are often used that require the knowledge
of supplementary parameters.
The reference and limit values are not included in this document.
2 Normative references
The following documents are referred to in the text in such a way that some or all of their content
constitutes requirements of this document. For dated references, only the edition cited applies. For
undated references, the latest edition of the referenced document (including any amendments) applies.
ISO/IEC Guide 98-3, Uncertainty of measurement — Part 3: Guide to the expression of uncertainty in
me a s ur ement (GUM: 1995)
ISO/IEC Guide 99, International vocabulary of metrology — Basic and general concepts and associated
terms (VIM)
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ISO 20043-1:2021(E)

ISO/IEC 17025, General requirements for the competence of testing and calibration laboratories
ISO 80000-10, Quantities and units — Part 10: Atomic and nuclear physics
3 Terms and definitions
For the purposes of this document, the definitions given in ISO 80000-10, ISO/IEC Guide 98-3,
ISO/IEC Guide 99, and the following 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 http:// www .electropedia .org/
3.1
background
doses, dose rates or activity concentrations associated with natural sources, or any other sources in the
environment that are not amenable to control
3.2
conversion coefficient
coefficient giving effective dose in an external exposure
3.3
data quality objectives
statement of the required detection limits, accuracy, reproducibility and repeatability of the required
analytical and other data
Note 1 to entry: Generic data quality objectives can sometimes be set at national level. Data quality objectives
can also embrace an amount of data required for an area of land (or part of a site) to enable sound comparison
with generic guidelines or standards or for a site-specific or material-specific estimation of risk.
3.4
dose assessment
assessment of the dose(s) to an individual or group of people
Note 1 to entry: For example, assessment of the dose received or committed by an individual on the basis of
results from workplace monitoring or bioassay.
Note 2 to entry: the term exposure assessment is also sometimes used.
3.5
dose coefficient
coefficient giving the committed effective dose from an internal exposure
3.6
emergency exposure situations
situation of exposure arising as a result of an accident, a malicious act or other unexpected event that
requires prompt action in order to avoid or to reduce adverse consequences
3.7
existing exposure situations
situation of exposure that already exists when a decision on the need for control needs to be taken
Note 1 to entry: Existing exposure situations include exposure to natural background radiation that is amenable
to control; exposure due to residual radioactive material that derives from past practices (3.13) that were never
subject to regulatory control; and exposure due to residual radioactive material deriving from a nuclear or
radiological emergency after an emergency has been declared to be ended.
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ISO 20043-1:2021(E)

3.8
hazard
potential for harm or detriment, especially for radiation risks; a factor or condition that might operate
against safety
3.9
intended use
use in accordance with information provided with a product or system, or, in the absence of such
information, by generally understood patterns of usage
3.10
model
analytical representation or quantification of a real system and the ways in which phenomena occur
within that system, used to predict or assess the behaviour of the real system under specified (often
hypothetical) conditions
[SOURCE: IAEA Safety Standard No. RS-G-1.8]
3.11
monitoring
measurement of dose, dose rate or activity for reasons relating to the assessment or control of exposure
to radiation or exposure due to radioactive substances, and the interpretation of the results
[SOURCE: IAEA Safety Glossary Terminology used in Nuclear Safety and Radiation Protection – 2018
Edition]
3.12
planned exposure situations
situation of exposure that arises from the planned operation of a source or from a planned activity that
results in an exposure due to a source
[SOURCE: IAEA Safety Glossary Terminology used in Nuclear Safety and Radiation Protection – 2018
Edition]
3.13
practice
human activity that introduces additional sources of exposure or exposure pathways or extends
exposure to additional people or modifies the network of exposure pathways from existing sources,
so as to increase the exposure or the likelihood of exposure of people or the number of people exposed
[SOURCE: IAEA Safety Standard No. RS–G–1.8]
3.14
quality assurance
planned and systematic actions necessary to provide adequate confidence that an item, process or
service satisfy given requirements for quality, for example, those specified in the license
[SOURCE: IAEA Safety Standard No. RS-G-1.8]
3.15
radioactive discharges
radioactive substances arising from a source (3.22) within a practice (3.13) which are discharged
as gases, aerosols, liquids or solids to the environment, generally with the purpose of dilution and
dispersion or disposal
[SOURCE: IAEA Safety Standard No. RS-G-1.8]
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ISO 20043-1:2021(E)

3.16
representative person
individual receiving a dose that is representative of the doses to the more highly exposed individuals in
the population
[SOURCE: ICRP Publication 101a. Annuals of the ICRP, 2006]
3.17
risk
combination of the probability of occurrence of harm and the severity of that harm
Note 1 to entry: The probability of occurrence includes the exposure to a hazardous situation, the occurrence of a
hazardous event and the possibility to avoid or limit the harm.
3.18
risk assessment
overall process comprising a risk analysis and a risk evaluation
3.19
screening
type of analysis aimed at eliminating from further consideration factors that are less significant for
protection or safety, in order to concentrate on the more significant factors
3.20
site
defined area, in this context often local target area
3.21
soil
surface layer of the Earth’s crust composed of mineral particles, including organic matter
3.22
source
anything that may cause radiation exposure, such as by emitting ionization or radiation or by relating
radioactive substances or materials, and can be treated as a single entry for protection and safety
purposes
Note 1 to entry: For example, materials emitting radon are sources in the environment, a sterilization gamma
irradiation unit is a source for the practice (3.13) of radiation preservation of food, an X ray unit may be a source for
the practice (3.13) of radiodiagnosis; a nuclear power plant is part of the practice (3.13) of generating electricity
by nuclear fission, and may be regarded as a source (e.g. with respect to discharges to the environment) or as
a collection of sources (e.g. for occupational radiation protection purposes). A complex or multiple installation
situated at one location or site may, as appropriate, be considered a single source for the purposes of application
of safety standards.
[SOURCE: IAEA Safety Standard No. RS-G-1.8]
3.23
surface soil
upper part of a natural soil, generally dark-coloured and with a higher content of organic substances
and nutrient when compared to the subsoil below
3.24
surface water
lakes, ponds, impounding reservoirs, springs, flowing (streaming) waters, estuaries, wetlands, inlets,
canals, oceans within the relevant territorial limits, and all other bodies of water, natural or artificial,
inland or coastal, fresh or salt
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ISO 20043-1:2021(E)

4 Symbols
a
At At +1  average activity concentration in air a of a rad
...