ISO/FDIS 18589-7
(Main)Measurement of radioactivity in the environment — Soil — Part 7: In situ measurement of gamma-emitting radionuclides
Measurement of radioactivity in the environment — Soil — Part 7: In situ measurement of gamma-emitting radionuclides
ISO 18589-7:2013 specifies the identification of radionuclides and the measurement of their activity in soil using in situ gamma spectrometry with portable systems equipped with germanium or scintillation detectors. ISO 18589-7:2013 is suitable to rapidly assess the activity of artificial and natural radionuclides deposited on or present in soil layers of large areas of a site under investigation. ISO 18589-7:2013 can be used in connection with radionuclide measurements of soil samples in the laboratory (ISO 18589‑3) in the following cases: · routine surveillance of the impact of radioactivity released from nuclear installations or of the evolution of radioactivity in the region; · investigations of accident and incident situations; · planning and surveillance of remedial action; · decommissioning of installations or the clearance of materials. It can also be used for the identification of airborne artificial radionuclides, when assessing the exposure levels inside buildings or during waste disposal operations. Following a nuclear accident, in situ gamma spectrometry is a powerful method for rapid evaluation of the gamma activity deposited onto the soil surface as well as the surficial contamination of flat objects.
Mesurage de la radioactivité dans l'environnement — Sol — Partie 7: Mesurage in situ des radionucléides émetteurs gamma
L'ISO 18589-7:2013 spécifie l'identification des radionucléides et la quantification de leur activité dans le sol en utilisant la spectrométrie gamma in situ avec des systèmes portatifs équipés de détecteurs au germanium ou à scintillations. L'ISO 18589-7:2013 est adaptée pour évaluer rapidement l'activité des radionucléides artificiels et naturels déposés ou présents dans des couches du sol d'un site soumis à l'étude. L'ISO 18589-7:2013 peut être utilisée en relation avec les mesurages de radionucléides des échantillons de sol au laboratoire [ISO 18589‑3] dans les cas suivants pour la surveillance en routine de l'impact de la radioactivité émanant d'installations nucléaires ou de l'évolution de la radioactivité du territoire, les investigations en situations d'accidents et d'incidents, la planification et la surveillance des actions de remédiation, et le déclassement d'installations ou l'élimination de matières nucléaires. L'ISO 18589-7:2013 peut également être utilisée pour identifier les radionucléides artificiels dans l'air, lors de l'évaluation des niveaux d'exposition à l'intérieur de bâtiments ou au cours des opérations d'élimination de déchets.
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Standards Content (Sample)
FINAL DRAFT
International
Standard
ISO/TC 85/SC 2
Measurement of radioactivity in the
Secretariat: AFNOR
environment — Soil —
Voting begins on:
Part 7:
In situ measurement of gamma-
Voting terminates on:
emitting radionuclides
Mesurage de la radioactivité dans l'environnement — Sol —
Partie 7: Mesurage in situ des radionucléides émetteurs gamma
RECIPIENTS OF THIS DRAFT ARE INVITED TO SUBMIT,
WITH THEIR COMMENTS, NOTIFICATION OF ANY
RELEVANT PATENT RIGHTS OF WHICH THEY ARE AWARE
AND TO PROVIDE SUPPOR TING DOCUMENTATION.
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TO BECOME STAN DARDS TO WHICH REFERENCE MAY BE
MADE IN NATIONAL REGULATIONS.
Reference number
FINAL DRAFT
International
Standard
ISO/TC 85/SC 2
Measurement of radioactivity in the
Secretariat: AFNOR
environment — Soil —
Voting begins on:
Part 7:
In situ measurement of gamma-
Voting terminates on:
emitting radionuclides
Mesurage de la radioactivité dans l'environnement — Sol —
Partie 7: Mesurage in situ des radionucléides émetteurs gamma
RECIPIENTS OF THIS DRAFT ARE INVITED TO SUBMIT,
WITH THEIR COMMENTS, NOTIFICATION OF ANY
RELEVANT PATENT RIGHTS OF WHICH THEY ARE AWARE
AND TO PROVIDE SUPPOR TING DOCUMENTATION.
© ISO 2025
IN ADDITION TO THEIR EVALUATION AS
All rights reserved. Unless otherwise specified, or required in the context of its implementation, no part of this publication may
BEING ACCEPTABLE FOR INDUSTRIAL, TECHNO-
ISO/CEN PARALLEL PROCESSING
LOGICAL, COMMERCIAL AND USER PURPOSES, DRAFT
be reproduced or utilized otherwise in any form or by any means, electronic or mechanical, including photocopying, or posting on
INTERNATIONAL STANDARDS MAY ON OCCASION HAVE
the internet or an intranet, without prior written permission. Permission can be requested from either ISO at the address below
TO BE CONSIDERED IN THE LIGHT OF THEIR POTENTIAL
or ISO’s member body in the country of the requester.
TO BECOME STAN DARDS TO WHICH REFERENCE MAY BE
MADE IN NATIONAL REGULATIONS.
ISO copyright office
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CH-1214 Vernier, Geneva
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Email: copyright@iso.org
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Published in Switzerland Reference number
ii
Contents Page
Foreword .v
Introduction .vi
1 Scope . 1
2 Normative references . 1
3 Terms and definitions . 1
4 Symbols . 3
5 Principles . 6
5.1 Measurement method .6
5.2 Uncertainties of the measurement method .7
6 Equipment . 7
6.1 Portable in situ spectrometry system .7
6.2 Detector system.7
6.2.1 General .7
6.2.2 Field-of-view .8
6.2.3 Special requirements.8
6.3 Pulse processing electronics .8
6.3.1 Components .8
6.3.2 Special requirements.9
6.3.3 Requirements for the evaluation program .9
6.4 Assembly jig for a detector system .10
6.5 Collimated detector .10
6.5.1 Construction.10
6.5.2 Collimator parameter .11
7 Procedure .12
7.1 Calibration . 12
7.2 Method of combined calibrations . 13
7.2.1 General . 13
7.2.2 Intrinsic efficiency .14
7.2.3 Geometry factor .14
7.2.4 Angular correction factor . 15
7.2.5 Numerical calibration procedure .16
8 Quality assurance and quality control program . 17
8.1 General .17
8.2 Influencing variables .17
8.3 Instrument verification .17
8.4 Method verification .17
8.5 Quality control program .18
8.5.1 General .18
8.5.2 Description of periodical quality checks .18
8.5.3 Measurement verification .18
8.5.4 Qualification .18
8.5.5 Documentation of quality controls .19
8.6 Standard operating procedure .19
9 Expression of results . 19
9.1 Calculation of activity per unit of surface area or unit of mass .19
9.2 Calculation of the characteristic limits and the best estimate of the measurand as well
as its standard uncertainty .19
9.2.1 General .19
9.2.2 Standard uncertainty . 20
9.2.3 Decision threshold and detection limit . 20
9.2.4 Limits of coverage interval and best estimate of the measurand .21
iii
9.3 Calculation of the radionuclide specific ambient dose rate .21
10 Test report .23
Annex A (informative) Influence of radionuclides in air on the result of surface or mass activity
measured by in situ gamma spectrometry .24
Annex B (informative) Influence quantities .25
Annex C (informative) Characteristics of germanium detectors .28
Annex D (informative) Field-of-view of an in situ gamma spectrometer as a function of the
photon energy for different radionuclide distributions in soil.30
Annex E (informative) Methods for calculating geometry factors and angular correction factors .34
Annex F (informative) Example for calculation of the characteristic limits as well as the best
estimate of the measurand and its standard uncertainty .42
Annex G (informative) Conversion factors for surface or mass activity to air kerma rate and
ambient dose equivalent rate for different radionuclide distribution in soil .46
Annex H (informative) Mass attenuation factors for soil and attenuation factors for air as a
function of photon energy and deviation of G(E,V) for different soil com
...
ISO /TC 85/SC 2/WG 17
Secretariat: AFNOR
Date: 2025-06-1908
Measurement of radioactivity in the environment — Soil — —
Part 7:
In situ measurement of gamma-emitting radionuclides
Mesurage de la radioactivité dans l'environnement — Sol —
Partie 7: Mesurage in situ des radionucléides émetteurs gamma
FDIS stage
All rights reserved. Unless otherwise specified, or required in the context of its implementation, no part of this publication
may be reproduced or utilized otherwise in any form or by any means, electronic or mechanical, including photocopying,
or posting on the internet or an intranet, without prior written permission. Permission can be requested from either ISO
at the address below or ISO’s member body in the country of the requester.
ISO copyright office
CP 401 • Ch. de Blandonnet 8
CH-1214 Vernier, Geneva
Phone: + 41 22 749 01 11
EmailE-mail: copyright@iso.org
Website: www.iso.org
Published in Switzerland
ii
Contents
Foreword . v
Introduction . vi
1 Scope . 1
2 Normative references . 1
3 Terms and definitions . 2
4 Symbols . 4
5 Principles . 6
5.1 Measurement method . 6
5.2 Uncertainties of the measurement method . 7
6 Equipment . 7
6.1 Portable in situ spectrometry system . 7
6.2 Detector system . 8
6.3 Pulse processing electronics . 9
6.4 Assembly jig for a detector system . 10
6.5 Collimated detector . 10
7 Procedure . 13
7.1 Calibration . 13
7.2 Method of combined calibrations . 14
8 Quality assurance and quality control program . 18
8.1 General . 18
8.2 Influencing variables . 18
8.3 Instrument verification . 18
8.4 Method verification . 18
8.5 Quality control program . 18
8.6 Standard operating procedure . 20
9 Expression of results . 20
9.1 Calculation of activity per unit of surface area or unit of mass . 20
9.2 Calculation of the characteristic limits and the best estimate of the measurand as well as
its standard uncertainty . 20
9.3 Calculation of the radionuclide specific ambient dose rate . 23
10 Test report . 24
Annex A (informative) Influence of radionuclides in air on the result of surface or mass activity
measured by in situ gamma spectrometry . 25
Annex B (informative) Influence quantities . 26
Annex C (informative) Characteristics of germanium detectors . 29
Annex D (informative) Field-of-view of an in situ gamma spectrometer as a function of the
photon energy for different radionuclide distributions in soil . 31
Annex E (informative) Methods for calculating geometry factors and angular correction factors35
Annex F (informative) Example for calculation of the characteristic limits as well as the best
estimate of the measurand and its standard uncertainty . 42
Annex G (informative) Conversion factors for surface or mass activity to air kerma rate and
ambient dose equivalent rate for different radionuclide distribution in soil . 46
iii
Annex H (informative) Mass attenuation factors for soil and attenuation factors for air as a
function of photon energy and deviation of G(E,V) for different soil compositions . 53
Bibliography . 55
iv
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).
ISO draws attention to the possibility that the implementation of this document may involve the use of (a)
patent(s). ISO takes no position concerning the evidence, validity or applicability of any claimed patent rights
in respect thereof. As of the date of publication of this document, ISO had not received notice of (a) patent(s)
which may be required to implement this document. However, implementers are cautioned that this may not
represent the latest information, which may be obtained from the patent database available at
www.iso.org/patents. ISO shall not be held responsible for identifying any or all such patent rights.
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 , TC 85, Nuclear energy, nuclear technologies, and
radiological protection, Subcommittee SC 2, Radiological protection., in collaboration with the European
Committee for Standardization (CEN) Technical Committee CEN/TC 430, Nuclear energy, nuclear technologies,
and radiological protection,in accordance with the Agreement on technical cooperation between ISO and CEN
(Vienna Agreement).
This second edition cancels and replaces the first edition (ISO 18549 18589-7:2013),), of which has been
technically revisedit constitutes a minor revision.
The main changes are as follows:
— B.10— B.10:: correction of the information related to the activity concentration of 40 K;
— E.2— E.2 and E.6E.6:: correction of 0Formulae (E.5) and 0(E.11);
— F.4— F.4 : correction of β, according to the numerical values of the example;
−2 −2
— F.6— F.6:: modify β = 50 g cm into β = 50 kg m ;
-2 -2 -2 -2
— G.3— G.3,, Footnote 1 of Table G.3Table G.3:: modify 1 g cm = 10 kg cm into 1 g cm = 10 kg m .
A list of all parts in the ISO 18589 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.
v
Introduction
In situ gamma spectrometry is a rapid and accurate technique to assess the activity concentration of gamma-
emitting radionuclides present in the top soil layer or deposited onto the soil surface. This method is also used
to assess the dose rates of individual radionuclides.
In situ gamma spectrometry is a direct physical measurement of radioactivity that does not need any soil
samples, thus reducing the time and cost of laboratory analysis of large number of soil samples.
The quantitative analysis of the recorded line spectra requires a suitable area for the measurement.
Furthermore, it is required to know the physicochemical properties of the soil and the vertical distribution in
the soil to assess the activity of the radionuclides.
vi
Measurement of radioactivity in the environment — Soil — Part 7: In
situ measurement of gamma emitting radionuclides — Soil —
Part 7:
In situ measurement of gamma-emitting radionuclides
1 Scope
This part of 18589document specifies the identification of radionuclides and the measurement of their activity
in soil using in situ gamma spectrometry with portable systems equipped with germanium or scintillation
detectors.
This part of ISO 18589document is suitable to rapidly assess the activity of artificial and natural radionuclides
deposited on or present in soil layers of large areas of a site under investigation.
This part of ISO 18589document can be used in connection with radionuclide measurements of soil samples
in the laboratory (see ISO 18589-3) in the following cases:
— — routine surveillance of the impact of radioactivity released from nuclear installations or of the
evolution of radioactivity in the region;
— — investigations of accident and incident situations;
— — planning and surveillance of remedial action;
— — decommissioning of installations or the clearance of materials.
It can also be used for the identification of airborne artificial radionuclides, when assessing the exposure levels
inside buildings or during waste disposal operations.
Following a nuclear accident, in situ gamma spectrometry is a powerful method for rapid evaluation of the
gamma activity deposited onto the soil surface as well as the surficial contamination of flat objects.
NOTE The method described in this part of ISO 18589document is not suitable when the spatial distribution of the
radionuclides in the environment is not precisely known (influence quantities, unknown distribution in soil) or in
situations with very high photon flux. However, the use of small volume detectors with suitable electronics allows
measurements to be performed under high photon flux.
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 17025, General requirements for the competence of testing and calibration laboratories
IEC 61275, Radiation protection instrumentation — Measurement of discrete radionuclides in the environment
— In situ photon spectrometry system using a germanium detector
ISO 11929 (all parts), Determination of the characteristic limits (decision threshold, detection limit and limits of
the cove
...
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