ISO 16638-1:2015

Radiological protection — Monitoring and internal dosimetry for specific materials — Part 1: Inhalation of uranium compounds

ISO 16638-1:2015 specifies the minimum requirements for the design of professional programmes to monitor workers exposed to uranium compounds. It establishes principles for the development of compatible goals and requirements for monitoring programmes and dose assessment for workers occupationally exposed to internal contamination. It establishes procedures and assumptions for risk analysis, monitoring programmes and the standardised interpretation of monitoring data in order to achieve acceptable levels of reliability for uranium and its compounds. It sets limits for the applicability of the procedures in respect to dose levels above which more sophisticated methods have to be applied. Uranium is both radiologically and chemically toxic. Hence, the scientific bases of current occupational exposure standards are reviewed in addition to radiation exposure limits. This International Standard addresses those circumstances when exposure could be constrained by either radiological or chemical toxicity concerns. ISO 16638-1:2015 addresses, for uranium and its compounds, the following items: a) purposes of monitoring and monitoring programmes; b) description of the different categories of monitoring programmes; c) quantitative criteria for conducting monitoring programmes; d) suitable methods for monitoring and criteria for their selection; e) information that has to be collected for the design of a monitoring programme; f) general requirements for monitoring programmes (e.g. detection limits, tolerated uncertainties); g) frequencies of measurements; h) procedures for dose assessment based on reference levels for routine and special monitoring programmes; i) assumptions for the selection of dose-critical parameter values; j) criteria for determining the significance of monitoring results; k) interpretation of workplace monitoring results; l) uncertainties arising from dose assessment and interpretation of bioassays data; m) reporting/documentation; n) quality assurance; o) record keeping requirements. It is not applicable to the following items: a) monitoring of exposure due to uranium progeny, including radon; b) detailed descriptions of measuring methods and techniques for uranium; c) dosimetry for litigation cases; d) modelling for the improvement of internal dosimetry; e) potential influence of counter-measures (e.g. administration of chelating agents); f) investigation of the causes or implications of an exposure; g) dosimetry for ingestion exposures and for contaminated wounds.

Radioprotection — Contrôle et dosimétrie interne des éléments spécifiques — Partie 1: Inhalation de composés d'uranium

L'ISO 16638-1:2015 décrit les exigences minimales permettant d'établir des programmes de surveillance professionnelle des travailleurs exposés aux composés de l'uranium. Elle établit les principes pour la mise en ?uvre des objectifs et des exigences des programmes de surveillance et de l'estimation dosimétrique des travailleurs exposés, dans cadre de leur travail, à une contamination interne. Elle établit des procédures et des hypothèses relatives à l'analyse des risques, aux programmes de surveillance et à l'interprétation normalisée des résultats de cette surveillance, afin d'atteindre des niveaux acceptables de fiabilité pour l'uranium et ses composés. Elle fixe des limites pour l'applicabilité des procédures concernant les niveaux de dose au-delà desquels des méthodes plus sophistiquées doivent être appliquées. L'uranium présente une toxicité à la fois radiologique et chimique. De ce fait, pour une exposition professionnelle, les bases scientifiques des conditions actuelles d'exposition au risque chimique sont revues au vu des limites d'exposition aux rayonnements ionisants. L'ISO 16638-1:2015 traite des circonstances dans lesquelles l'exposition peut être assujettie aux problèmes liés à la toxicité radiologique ou chimique. L'ISO 16638-1:2015 aborde, pour l'uranium et ses composés, les points suivants: a) les objectifs de la surveillance et les programmes de surveillance; b) la description des différentes catégories de programmes de surveillance; c) les critères quantitatifs pour la conduite des programmes de surveillance; d) les méthodes valables pour la surveillance et leurs critères de sélection; e) les informations à collecter pour l'élaboration d'un programme de surveillance; f) les exigences générales pour les programmes de surveillance (par exemple limites de détection, incertitudes tolérées); g) les fréquences des mesurages; h) les procédures d'estimation dosimétrique basées sur les niveaux de référence utilisés pour les programmes de surveillance de routine et spéciale; i) les hypothèses concernant la sélection des valeurs des paramètres critiques de dose; j) les critères pour la détermination de l'importance des résultats de la surveillance; k) l'interprétation des résultats de la surveillance aux postes de travail; l) les incertitudes liées à l'estimation dosimétrique et l'interprétation des résultats sur échantillons biologiques; m) la transmission et la documentation; n) l'assurance de la qualité; o) les exigences en matière de conservation des enregistrements. Le domaine d'application de la présente Norme internationale n'inclut pas les éléments suivants: a) la surveillance de l'exposition aux descendants de l'uranium, y compris le radon; b) les descriptions détaillées des méthodes et des techniques de mesurage concernant l'uranium; c) la dosimétrie des cas litigieux; d) la modélisation pour l'amélioration de la dosimétrie interne; e) l'influence potentielle de l'action des agents décorporants (par exemple, administration d'agents complexants); f) l'investigation des causes et des conséquences d'une exposition; g) la dosimétrie pour les expositions par ingestion et par blessures contaminées.

General Information

• Status: Published
• Publication Date: 08-Dec-2015
• ICS: 17.240 - Radiation measurements
• Technical Committee: ISO/TC 85/SC 2 - Radiological protection
• Drafting Committee: ISO/TC 85/SC 2/WG 13 - Monitoring and dosimetry for internal exposure
• Current Stage: 9092 - International Standard to be revised
• Start Date: 14-Jul-2025
• Completion Date: 19-Jul-2025

Standards Content (Sample)

DRAFT INTERNATIONAL STANDARD
ISO/DIS 16638-1
ISO/TC 85/SC 2 Secretariat: AFNOR
Voting begins on: Voting terminates on:
2014-03-17 2014-06-17
Radiological protection - Monitoring and internal
dosimetry for specific materials —
Part 1:
Uranium
Radioprotection - Contrôle et dosimétrie interne des éléments spécifiques —
Partie 1: Uranium
ICS: 17.240
THIS DOCUMENT IS A DRAFT CIRCULATED
FOR COMMENT AND APPROVAL. IT IS
THEREFORE SUBJECT TO CHANGE AND MAY
NOT BE REFERRED TO AS AN INTERNATIONAL
STANDARD UNTIL PUBLISHED AS SUCH.
IN ADDITION TO THEIR EVALUATION AS
BEING ACCEPTABLE FOR INDUSTRIAL,
TECHNOLOGICAL, COMMERCIAL AND
USER PURPOSES, DRAFT INTERNATIONAL
STANDARDS MAY ON OCCASION HAVE TO
BE CONSIDERED IN THE LIGHT OF THEIR
POTENTIAL TO BECOME STANDARDS TO
WHICH REFERENCE MAY BE MADE IN
Reference number
NATIONAL REGULATIONS.
ISO/DIS 16638-1:2014(E)
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 SUPPORTING DOCUMENTATION. ISO 2014

ISO/DIS 16638-1:2014(E)
Copyright notice
This ISO document is a Draft International Standard and is copyright-protected by ISO. Except as
permitted under the applicable laws of the user’s country, neither this ISO draft nor any extract
from it may be reproduced, stored in a retrieval system or transmitted in any form or by any means,
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Reproduction may be subject to royalty payments or a licensing agreement.
Violators may be prosecuted.
ii © ISO 2014 – All rights reserved

ISO/DIS 16638-1
Contents Page
Foreword . iv
Introduction . v
1 Scope . 1
2 Normative references . 2
3 Terms and definitions . 2
4 Symbols and abbreviated terms . 6
5 Purpose and need for monitoring programmes . 7
6 General aspects . 10
7 Reference levels for uranium . 11
8 Routine monitoring programmes . 16
9 Special monitoring programmes . 19
10 Task-related monitoring programmes . 21
11 Performance criteria for laboratories . 22
12 Quality assurance and quality control for bioassay laboratories . 24
13 Procedure for the assessment of exposures . 25
14 Reporting and documentation . 27
Annex A (informative) Nuclear data of U-238 and U-235 decay . 30
Annex B (informative) Default classification of uranium compounds . 31
Annex C (informative) Measurements techniques for uranium . 32
Annex D (informative) Committed effective dose par unit intake for uranium compounds . 36
Annex E (informative) Estimation of uncertainties for internal dose assessments. 37
Bibliography . 41

ISO/DIS 16638-1
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.
International Standards are drafted in accordance with the rules given in the ISO/IEC Directives, Part 2.
The main task of technical committees is to prepare International Standards. Draft International Standards
adopted by the technical committees are circulated to the member bodies for voting. Publication as an
International Standard requires approval by at least 75 % of the member bodies casting a vote.
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.
ISO 16638-1 was prepared by Technical Committee ISO/TC 85, Nuclear energy, nuclear technologies, and
radiological protection, Subcommittee SC 2, Radiological protection.
This second/third/. edition cancels and replaces the first/second/. edition (), [clause(s) / subclause(s) /
table(s) / figure(s) / annex(es)] of which [has / have] been technically revised.
ISO 16638 consists of the following parts, under the general title Radiological protection — Monitoring and
internal dosimetry for specific materials:
 Part 1: Uranium
iv © ISO 2013 – All rights reserved

ISO/DIS 16638-1
Introduction
In the course of employment, individuals may work with radioactive materials that, under certain
circumstances, could be taken into the body. Protecting workers against risks of incorporated radionuclides
requires the monitoring of potential intakes and/or the quantification of actual intakes and exposures. The
doses resulting from internal radiation exposure arising from contamination by radioactive substances cannot
be measured directly. The selection of measures and programmes for this purpose requires decisions
concerning methods, techniques, frequencies etc. for measurements and dose assessment. The criteria
permitting the evaluation of the necessity of such a monitoring programme or for the selection of methods and
frequencies of monitoring usually depend upon legislation, the purpose of the radiation protection programme,
the probabilities of potential radionuclide intakes, and the characteristics of the materials handled.
For these reasons, three ISO standards addressing laboratory requirements (28218:2010), monitoring
programmes (20553:2006) and dose assessments (27048:2011) have been developed and can be applied in
a straightforward manner to many radionuclides. However, for a number of specific materials, their practical
application is complex and further guidance may be required, e.g for accreditation purposes. Such guidance
was requested by a number of countries during the consultation phase for these standards.
Monitoring and internal dosimetry for uranium and its compounds are addressed in this standard because of:
 the growing interest in nuclear energy production and the associated increase in uranium mining and fuel
production;
 the large variation of isotopic compositions of the compounds that may be encountered in the workplace;
and,
 the importance of taking into account both the chemical and the radiological risks arising from exposures
to uranium.
An ISO standard that addresses the specific issue of monitoring and internal dosimetry for uranium will
contribute to harmonising monitoring of occupationally exposed persons while remaining complementary to
the three earlier standards.
This International Standard offers guidance on the need for a monitoring and internal dosimetry programme
for the different compounds of uranium and how it should be designed. Recommendations of international
expert bodies and international experience with the practical application of these recommendations in
radiological protection programmes have been considered in the development of this International Standard.
Its application facilitates the exchanges of information between authorities, supervisory institutions and
employers. The International Standard is not a substitute for legal requirements.

DRAFT INTERNATIONAL STANDARD ISO/DIS 16638-1

Radiological protection — Monitoring and internal dosimetry for
specific materials — Part 1: Uranium
1 Scope
This International Standard specifies the minimum requirements for the design of professional programmes to
monitor workers exposed to the different compounds of uranium and establishes principles for the
development of compatible goals and requirements for monitoring programmes and the dose assessment for
workers occupationally exposed to the risk of internal contamination. It presents procedures and assumptions
for the risk analysis, for the monitoring programmes and for the standardised interpretation of monitoring data,
in order to achieve acceptable levels of reliability for uranium and its compounds. Limits are set for the
applicability of the procedures in respect of the dose levels above which more sophisticated methods have to
be applied.
Uranium is both radiologically and chemically toxic. Hence the bases of current occupational exposure
standards are reviewed in addition to radiation exposure limits. This standard addresses those circumstances
when exposure could be constrained by either radiological or chemical toxicity concerns.
This International Standard addresses, for uranium and its compounds the following items:
a) purposes of monitoring and of monitoring programmes;
b) description of the different categories of monitoring programmes;
c) quantitative criteria for conducting monitoring programmes;
d) suitable methods for monitoring and criteria for their selection;
e) information that has to be collected for the design of a monitoring programme;
f) general requirements for monitoring programmes (e.g. detection limits, tolerated uncertainties);
g) frequencies of measurements;
h) procedures for dose assessment based on reference levels for routine and special monitoring
programmes;
i) assumptions for the selection of dose-critical parameter values;
j) criteria for determining the significance of monitoring results;
k) interpretation of workplace monitoring results;
l) uncertainties arising from dose assessments and interpretation of bioassays data;
m) reporting/documentation;
n) quality assurance.
ISO/DIS 16638-1
It is not applicable to the following:
a) the monitoring of exposure uranium progeny including radon;
b) detailed descriptions of measuring methods and techniques for uranium;
c) dosimetry for litigation cases;
d) modelling for the improvement of internal dosimetry;
e) the potential influence of counter-measures (e.g. administration of chelating agents);
f) the investigation of the causes or implications of an exposure;
g) dosimetry for ingestion exposures and for contaminated wounds
2 Normative references
The following documents, in whole or in part, are normatively referenced in this document and are
indispensable for its application. 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
measurement (GUM:1995)
ISO/IEC Guide 99, International vocabulary of metrology — Basic and general concepts and associated terms
(VIM)
ISO 5725-1, Accuracy (trueness and precision) of measurement methods and results — Part 1: General
principles and definitions
ISO 5725-2, Accuracy (trueness and precision) of measurement methods and results — Part 2: Basic method
for the determination of repeatability and reproducibility of a standard measurement method
ISO 5725-3, Accuracy (trueness and precision) of measurement methods and results — Part 3: Intermediate
measures of the precision of a standard measurement method
ISO 20553:2006, Radiation protection — Monitoring of workers occupationally exposed to a risk of internal
contamination with radioactive material
ISO 28218:2010, Radiation protection — Performance criteria for radiobioassay
ISO 27048:2011, Radiation protection — Dose assessment for the monitoring of workers for internal radiation
exposure
3 Terms and definitions
For the purposes of this document, the terms and definitions given in ISO/IEC Guide 99, ISO 5725-1,
ISO 5725-2, ISO 5725-3, and in Publications of ICRP and ICRU [6,7,8,9,10,11,12,13,14,15,16,17,18,19 and
20] and the following apply.
3.1
absorption
transfer of material from lungs to body fluids, characterised by its rate.
Note 1 to entry: In the absence of absorption rate values for specific radionuclide compounds, default values of type F,
M and S can be applied.
ISO/DIS 16638-1
3.2
absorption type F
depo
...

INTERNATIONAL ISO
STANDARD 16638-1
First edition
2015-12-15
Radiological protection —
Monitoring and internal dosimetry
for specific materials —
Part 1:
Inhalation of uranium compounds
Radioprotection — Contrôle et dosimétrie interne des éléments
spécifiques —
Partie 1: Inhalation de composés d’uranium
Reference number
©
ISO 2015
© ISO 2015, Published in Switzerland
All rights reserved. Unless otherwise specified, 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
Ch. de Blandonnet 8 • CP 401
CH-1214 Vernier, Geneva, Switzerland
Tel. [phone]
Fax [phone]
[e-mail]
www.iso.org
ii © ISO 2015 – All rights reserved

Contents Page
Foreword .v
Introduction .vi
1 Scope . 1
2 Normative references . 2
3 Terms and definitions . 2
4 Symbols and abbreviated terms . 6
4.1 Symbols . 6
4.2 Abbreviated terms . 7
5 Purpose and need for monitoring programmes . 7
6 General aspects .10
6.1 Radiological aspects .10
6.2 Chemical toxicity .11
7 Reference levels for uranium .12
7.1 Radiological aspects .12
7.2 Chemical toxicity .15
7.2.1 General.15
7.2.2 Exposure limits .15
7.3 Application of reference levels .16
8 Routine monitoring programmes .16
8.1 General .16
8.2 Workplace monitoring . .16
8.3 Individual monitoring .17
8.3.1 General.17
8.3.2 Dosimetric and radiation .17
8.3.3 Chemical hazard .18
8.4 Methods and monitoring intervals .18
8.4.1 General.18
8.4.2 Time intervals for toxicological risk.18
8.4.3 Time intervals for radiotoxicological risk .18
8.4.4 Principles and assumptions .19
9 Special monitoring programmes .20
9.1 Workplace monitoring . .20
9.2 Individual monitoring .20
9.2.1 Recommended monitoring for toxicological risk .20
9.2.2 Recommended monitoring and period for radiotoxicological risk .20
10 Task-related monitoring programmes .21
10.1 Workplace monitoring . .21
10.2 Individual monitoring .21
11 Performance criteria for laboratories .22
11.1 General .22
11.2 Critical values .22
11.3 Reference values .23
11.4 Performance criteria for workplace monitoring .23
12 Quality assurance and quality control for bioassay laboratories .24
13 Procedure for the assessment of exposures .24
13.1 General .24
13.2 Assessment of workplace monitoring data .25
13.3 Assessment of individual monitoring data .25
13.4 Properties of a software tool .25
13.5 Uncertainties .26
13.6 Quality assurance of the assessment process .27
14 Reporting and documentation .27
14.1 Reporting results for in vitro measurements .27
14.2 Reporting results for in vivo measurements .28
14.3 Documentation of the dose assessment .28
Annex A (informative) Nuclear data of U-238 and U-235 decay .30
Annex B (informative) Default classification of uranium compounds .31
Annex C (informative) Measurement techniques for uranium .32
Annex D (informative) Committed effective dose per unit intake for uranium compounds .36
Annex E (informative) Estimation of uncertainties for internal dose assessments .37
Bibliography .41
iv © ISO 2015 – All rights reserved

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 WTO principles in the Technical
Barriers to Trade (TBT) see the following URL: Foreword - Supplementary information
The committee responsible for this document is ISO/TC 85, Nuclear energy, nuclear technologies, and
radiological protection, Subcommittee SC 2, Radiological protection.
Introduction
In the course of employment, individuals may work with radioactive materials that, under certain
circumstances, could be taken into the body. Protecting workers against the risks of incorporated
radionuclides requires monitoring potential intakes and/or quantifying actual intakes and exposure
...

NORME ISO
INTERNATIONALE 16638-1
Première édition
2015-12-15
Radioprotection — Contrôle et
dosimétrie interne des éléments
spécifiques —
Partie 1:
Inhalation de composés d’uranium
Radiological protection — Monitoring and internal dosimetry for
specific materials —
Part 1: Inhalation of uranium compounds
Numéro de référence
©
ISO 2015
DOCUMENT PROTÉGÉ PAR COPYRIGHT
© ISO 2015, Publié en Suisse
Droits de reproduction réservés. Sauf indication contraire, aucune partie de cette publication ne peut être reproduite ni utilisée
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l’adresse ci-après ou au comité membre de l’ISO dans le pays du demandeur.
ISO copyright office
Ch. de Blandonnet 8 • CP 401
CH-1214 Vernier, Geneva, Switzerland
Tel. [phone]
Fax [phone]
[e-mail]
www.iso.org
ii © ISO 2015 – Tous droits réservés

Sommaire Page
Avant-propos .v
Introduction .vi
1 Domaine d’application . 1
2 Références normatives . 2
3  Termes et définitions . 2
4 Symboles et termes abrégés . 7
4.1 Symboles . 7
4.2 Termes abrégés . 7
5  Objectif et nécessité des programmes de surveillance. 8
6  Aspects généraux .11
6.1 Aspects radiologiques .11
6.2 Toxicité chimique .12
7  Niveaux de référence pour l’uranium .13
7.1 Aspects radiologiques .13
7.2 Toxicité chimique .16
7.2.1 Généralités .16
7.2.2 Limites d’exposition .17
7.3 Application des niveaux de référence .18
8  Programmes de surveillance de routine .18
8.1 Généralités .18
8.2 Surveillance aux postes de travail .18
8.3 Surveillance individuelle .19
8.3.1 Généralités .19
8.3.2 Risque radiotoxicologique .19
8.3.3 Risque chimique .20
8.4 Méthodes et intervalles de surveillance .20
8.4.1 Généralités .20
8.4.2 Intervalles de surveillance pour le risque toxicologique .20
8.4.3 Intervalles de surveillance pour le risque radiotoxicologique .20
8.4.4 Principes et hypothèses .21
9  Programmes de surveillance spéciale.22
9.1 Surveillance aux postes de travail .22
9.2 Surveillance individuelle .22
9.2.1 Surveillance recommandée pour le risque toxicologique .22
9.2.2 Surveillance et période recommandées pour le risque radiotoxicologique .23
10  Programmes de surveillance de chantier .24
10.1 Surveillance aux postes de travail .24
10.2 Surveillance individuelle .24
11  Critères de performance pour les laboratoires de biologie médicale .24
11.1 Généralités .24
11.2 Valeurs critiques .24
11.3 Valeurs de référence .25
11.4 Critères de performance concernant la surveillance aux postes de travail .26
12  Assurance et contrôle de la qualité dans les laboratoires d’analyses médicales .26
13  Procédure d’évaluation des expositions .27
13.1 Généralités .27
13.2 Évaluation des données de la surveillance aux postes de travail .28
13.3 Évaluation des données de la surveillance individuelle .28
13.4 Propriétés d’un outil logiciel .28
13.5 Incertitudes .29
13.6 Assurance de la qualité du processus d’estimation .30
14  Transmission des résultats et documentation .30
14.1 Transmission des résultats relatifs aux analyses in vitro .30
14.2 Transmission des résultats relatifs aux examens in vivo .31
14.3 Documentation de l’estimation dosimétrique .31
Annexe A (informative) Données nucléaires des isotopes U-238 et U-235 .33
Annexe B (informative) Classification par défaut des composés de l’uranium .34
Annexe C (informative) Techniques de mesure de l’uranium .36
Annexe D (informative) Dose efficace engagée par unité d’incorporation pour les composés
de l’uranium .41
Annexe E (informative) Estimation des incertitudes relatives aux estimations
dosimétriques internes .42
Bibliographie .46
iv © ISO 2015 – Tous droits réservés

Avant-propos
L’ISO (Organisation internationale de normalisation) est une fédération mondiale d’organismes
nationaux de normalisation (comités membres de l’ISO). L’élaboration des Normes internationales est
en général confiée aux comités techniques de l’ISO. Chaque comité membre intéressé par une étude
a le droit de faire partie du comité technique créé à cet effet. Les organisations internationales,
gouvernementales et non gouvernementales, en liaison avec l’ISO participent également aux travaux.
L’ISO collabore étroitement avec la Commission électrotechnique internationale (IEC) en ce qui
concerne la normalisation électrotechnique.
Les procédures utilisées pour élaborer le présent document et celles destinées à sa mise à jour sont
décrites dans les Directives ISO/IEC, Partie 1. Il convient, en particulier de prendre note des différents
critères d’approbation requis pour les différents types de documents ISO. Le présent document a été
rédigé conformément aux règles de rédaction données dans les Directives ISO/IEC, Partie 2 (voir www.
iso.org/directives).
L’attention est appelée sur le fait que certains des éléments du présent document peuvent faire l’objet de
droits de propriété intellectuelle ou de droits analogues. L’ISO ne saurait être tenue pour responsable
de ne pas avoir identifié de tels droits de propriété et averti de leur existence. Les détails concernant
les références aux droits de propriété intellectuelle ou autres droits analogues identifiés lors de
l’élaboration du document sont indiqués dans l’Introduction et/ou dans la liste des déclarations de
brevets reçues par l’ISO (voir www.iso.org/brevets).
Les appellations commerciales éventuellement mentionnées dans le présent document sont données
pour information, par souci de commodité à l’intention des utilisateurs et ne sauraient constituer un
engagement.
Pour une explication de la signification des termes et expressions spécifiques de l’ISO liés à l’évaluation
de la conformité, ou pour toute information au sujet de l’adhésion de l’ISO aux principes de l’Organisation
mondiale du commerce (OMC) concernant les obstacles techniques au commerce (OTC) voir le lien
suivant: www.iso.org/iso/fr/foreword.html.
Le comité chargé de l’élaboration du présent document est l’ISO/TC 85, Énergie nucléaire, technologies
nucléaires et radioprotection, sous-comité SC 2, Radioprotection.
Intro
...