Radiological protection - Monitoring and internal dosimetry for staff members exposed to medical radionuclides as unsealed sources (ISO 16637:2016)

ISO 16637:2016 specifies the minimum requirements for the design of professional programmes to monitor workers exposed to the risk of internal contamination via inhalation by the use of radionuclides as unsealed sources in nuclear medicine imaging and therapy departments. It establishes principles for the development of compatible goals and requirements for monitoring programmes and, when adequate, dose assessment. It presents procedures and assumptions for the risk analysis, for the monitoring programmes, and for the standardized interpretation of monitoring data.
ISO 16637:2016 addresses 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 individual 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 16637:2016 does not address the following:
-      monitoring and internal dosimetry for the workers exposed to laboratory use of radionuclides such as radioimmunoassay techniques;
-      monitoring and internal dosimetry for the workers involved in the operation, maintenance, and servicing of PET cyclotrons;
-      detailed descriptions of measuring methods and techniques;
-      dosimetry for litigation cases;
-      modelling for the improvement of internal dosimetry;
-      the potential influence of medical treatment of the internal contamination;
-      the investigation of the causes or implications of an exposure;
-      dosimetry for ingestion exposures and for contaminated wounds.

Strahlenschutz - Überwachung und interne Dosimetrie für Beschäftigte, die durch medizinisch genutzte Radionuklide aus offenen Quellen exponiert wurden (ISO 16637:2016)

Radioprotection - Surveillance et dosimétrie interne des travailleurs exposés lors des utilisations médicales des radioéléments en sources non scellées (ISO 16637:2016)

L'ISO 16637:2016 décrit les exigences minimales permettant d'établir des programmes de surveillance professionnelle des travailleurs exposés à un risque de contamination interne par inhalation lors de l'utilisation, à des fins diagnostiques ou thérapeutiques, de radionucléides en sources non scellées dans les services de médecine nucléaire. Elle établit des principes pour l'élaboration d'objectifs et d'exigences compatibles avec les programmes de surveillance et, le cas échéant, l'estimation de la dose. Elle présente les procédures et les hypothèses considérées pour l'analyse du risque, pour la mise en place des programmes de surveillance et pour l'interprétation normalisée des données de surveillance.
L'ISO 16637:2016 traite des points suivants:
a)    objectifs de la surveillance et des programmes de surveillance;
b)    description des différentes catégories de programmes de surveillance;
c)    critères quantitatifs pour la conduite des programmes de surveillance;
d)    méthodes valables pour la surveillance et leurs critères de sélection;
e)    informations à collecter pour l'élaboration d'un programme de surveillance;
f)     exigences générales pour les programmes de surveillance (par exemple? limites de détection, incertitudes tolérées);
g)    fréquence des mesurages;
h)    procédures d'estimation dosimétrique fondées sur des niveaux de référence pour les programmes de surveillance de routine et post-incidentelle;
i)     hypothèses pour le choix des paramètres influençant l'estimation dosimétrique;
j)     critères pour déterminer si les résultats de la surveillance individuelle sont significatifs;
k)    interprétation des résultats de la surveillance aux postes de travail;
l)     incertitudes liées aux estimations de la dose et à l'interprétation des données de mesurage in vivo et d'analyse in vitro;
m)   compte-rendu/documentation;
n)    assurance de la qualité.
L'ISO 16637:2016 ne traite pas des points suivants:
- surveillance et dosimétrie interne pour les travailleurs exposés lors des utilisations en laboratoire de radionucléides, par exemple lors des dosages radio-immunologiques;
- surveillance et dosimétrie interne pour les travailleurs impliqués dans l'exploitation, la maintenance et l'entretien des cyclotrons TEP;
- descriptions détaillées des méthodes et techniques de mesurage;
- dosimétrie dans les cas litigieux;
- modélisation pour l'amélioration de la dosimétrie interne;
- influence potentielle d'un traitement médical de la contamination interne;
- investigation des causes ou des conséquences d'une exposition;
- dosimétrie pour les expositions par ingestion et par plaies contaminées.

Radiološka zaščita - Nadzorovanje in notranja dozimetrija za člane osebja, izpostavljene medicinskim radionuklidom kot odprtemu viru sevanja (ISO 16637:2016)

Standard ISO 16645:2016 se uporablja za medicinske elektronske linearne pospeševalnike, tj. linearne pospeševalnike z nominalnimi energijami žarka od 4 MV do 30 MV, vključno s posebnimi instalacijami, kot so robotska roka, radioterapevtske naprave, ki so modulirane s spiralno intenziteto, in naprave, namenjene za medoperacijsko radioterapijo (IORT) z elektroni.
Ciklotroni in sinhrotroni, ki se uporabljajo pri hadronski terapiji, niso upoštevani v tem dokumentu.
Zahteve in priporočila za radiološko zaščito, ki so podani v standardu ISO 16645:2016, obravnavajo vidike, povezane s predpisi, cilji snovanja zaščitnih zaslonov in drugih kriterijev snovanja, vlogo izdelovalcev, pooblaščenega izvedenca varstva pred sevanji ali usposobljenega strokovnjaka ter interakcijami med deležniki, sevanjem okoli linearnega pospeševalnika, zaščito za konvencionalne in posebne naprave (vključno z zaščitnimi materiali in vrednostmi transmisije, izračuni za različne konfiguracije ambulant, vpliv cevi na radiološko zaščito) ter nadzorom sevanja (meritve).

General Information

Status
Published
Publication Date
11-Jun-2019
Current Stage
6060 - Definitive text made available (DAV) - Publishing
Due Date
12-Jun-2019
Completion Date
12-Jun-2019

Buy Standard

Standard
EN ISO 16637:2019 - BARVE na PDF-str 21
English language
37 pages
sale 10% off
Preview
sale 10% off
Preview
e-Library read for
1 day

Standards Content (sample)

SLOVENSKI STANDARD
SIST EN ISO 16637:2019
01-september-2019
Radiološka zaščita - Nadzorovanje in notranja dozimetrija za člane osebja,
izpostavljene medicinskim radionuklidom kot odprtemu viru sevanja (ISO
16637:2016)

Radiological protection - Monitoring and internal dosimetry for staff members exposed to

medical radionuclides as unsealed sources (ISO 16637:2016)
Strahlenschutz - Überwachung und interne Dosimetrie für Personal, das durch
medizinische Radionuklide aus offenen Quellen exponiert wurde (ISO 16637:2016)

Radioprotection - Surveillance et dosimétrie interne des travailleurs exposés lors des

utilisations médicales des radioéléments en sources non scellées (ISO 16637:2016)

Ta slovenski standard je istoveten z: EN ISO 16637:2019
ICS:
13.280 Varstvo pred sevanjem Radiation protection
SIST EN ISO 16637:2019 en,fr,de

2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

---------------------- Page: 1 ----------------------
SIST EN ISO 16637:2019
---------------------- Page: 2 ----------------------
SIST EN ISO 16637:2019
EN ISO 16637
EUROPEAN STANDARD
NORME EUROPÉENNE
June 2019
EUROPÄISCHE NORM
ICS 13.280
English Version
Radiological protection - Monitoring and internal
dosimetry for staff members exposed to medical
radionuclides as unsealed sources (ISO 16637:2016)

Radioprotection - Surveillance et dosimétrie interne Strahlenschutz - Überwachung und interne Dosimetrie

des travailleurs exposés lors des utilisations médicales für Personal, das durch medizinische Radionuklide aus

des radioéléments en sources non scellées (ISO offenen Quellen exponiert wurde (ISO 16637:2016)

16637:2016)
This European Standard was approved by CEN on 8 March 2019.

CEN members are bound to comply with the CEN/CENELEC Internal Regulations which stipulate the conditions for giving this

European Standard the status of a national standard without any alteration. Up-to-date lists and bibliographical references

concerning such national standards may be obtained on application to the CEN-CENELEC Management Centre or to any CEN

member.

This European Standard exists in three official versions (English, French, German). A version in any other language made by

translation under the responsibility of a CEN member into its own language and notified to the CEN-CENELEC Management

Centre has the same status as the official versions.

CEN members are the national standards bodies of Austria, Belgium, Bulgaria, Croatia, Cyprus, Czech Republic, Denmark, Estonia,

Finland, Former Yugoslav Republic of Macedonia, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania,

Luxembourg, Malta, Netherlands, Norway, Poland, Portugal, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland,

Turkey and United Kingdom.
EUROPEAN COMMITTEE FOR STANDARDIZATION
COMITÉ EUROPÉEN DE NORMALISATION
EUROPÄISCHES KOMITEE FÜR NORMUNG
CEN-CENELEC Management Centre: Rue de la Science 23, B-1040 Brussels

© 2019 CEN All rights of exploitation in any form and by any means reserved Ref. No. EN ISO 16637:2019 E

worldwide for CEN national Members.
---------------------- Page: 3 ----------------------
SIST EN ISO 16637:2019
EN ISO 16637:2019 (E)
Contents Page

European foreword ....................................................................................................................................................... 3

---------------------- Page: 4 ----------------------
SIST EN ISO 16637:2019
EN ISO 16637:2019 (E)
European foreword

The text of ISO 16637:2016 has been prepared by Technical Committee ISO/TC 85 "Nuclear energy,

nuclear technologies, and radiological protection” of the International Organization for Standardization

(ISO) and has been taken over as EN ISO 16637:2019 by Technical Committee CEN/TC 430 “Nuclear

energy, nuclear technologies, and radiological protection” the secretariat of which is held by AFNOR.

This European Standard shall be given the status of a national standard, either by publication of an

identical text or by endorsement, at the latest by December 2019, and conflicting national standards

shall be withdrawn at the latest by December 2019.

Attention is drawn to the possibility that some of the elements of this document may be the subject of

patent rights. CEN shall not be held responsible for identifying any or all such patent rights.

According to the CEN-CENELEC Internal Regulations, the national standards organizations of the

following countries are bound to implement this European Standard: Austria, Belgium, Bulgaria,

Croatia, Cyprus, Czech Republic, Denmark, Estonia, Finland, Former Yugoslav Republic of Macedonia,

France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta,

Netherlands, Norway, Poland, Portugal, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland,

Turkey and the United Kingdom.
Endorsement notice

The text of ISO 16637:2016 has been approved by CEN as EN ISO 16637:2019 without any modification.

---------------------- Page: 5 ----------------------
SIST EN ISO 16637:2019
---------------------- Page: 6 ----------------------
SIST EN ISO 16637:2019
INTERNATIONAL ISO
STANDARD 16637
First edition
2016-02-15
Radiological protection — Monitoring
and internal dosimetry for staff
members exposed to medical
radionuclides as unsealed sources
Radioprotection — Surveillance et dosimétrie interne des travailleurs
exposés lors des utilisations médicales des radioéléments en sources
non scellées
Reference number
ISO 16637:2016(E)
ISO 2016
---------------------- Page: 7 ----------------------
SIST EN ISO 16637:2019
ISO 16637:2016(E)
COPYRIGHT PROTECTED DOCUMENT
© ISO 2016, 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. +41 22 749 01 11
Fax +41 22 749 09 47
copyright@iso.org
www.iso.org
ii © ISO 2016 – All rights reserved
---------------------- Page: 8 ----------------------
SIST EN ISO 16637:2019
ISO 16637:2016(E)
Contents Page

Foreword ..........................................................................................................................................................................................................................................v

Introduction ................................................................................................................................................................................................................................vi

1 Scope ................................................................................................................................................................................................................................. 1

2 Normative references ...................................................................................................................................................................................... 2

3 Terms and definitions ..................................................................................................................................................................................... 2

4 Symbols and abbreviated terms ........................................................................................................................................................... 5

5 Purpose and need for monitoring programmes in nuclear medical diagnosis and therapy 6

5.1 General ........................................................................................................................................................................................................... 6

5.2 Assessment of the level of likely exposures ................................................................................................................... 6

5.3 Monitoring programmes ................................................................................................................................................................ 7

5.3.1 General...................................................................................................................................................................................... 7

5.3.2 Confirmatory monitoring programmes ....................................................................................................... 7

5.3.3 Routine monitoring programmes...................................................................................................................... 8

5.3.4 Triage monitoring programmes ......................................................................................................................... 8

5.3.5 Task-related monitoring programmes .......................................................................................................... 8

5.3.6 Special monitoring programmes ....................................................................................................................... 8

5.3.7 Implementation of a monitoring programme......................................................................................... 9

6 Common radionuclides ...............................................................................................................................................................................10

7 Reference levels ..................................................................................................................................................................................................10

8 Routine monitoring programmes ....................................................................................................................................................11

8.1 General aspects ....................................................................................................................................................................................11

8.2 Individual monitoring ....................................................................................................................................................................12

8.3 Methods and monitoring intervals .....................................................................................................................................12

9 Triage monitoring programmes ........................................................................................................................................................13

10 Special Monitoring programmes ......................................................................................................................................................13

10.1 General aspects ....................................................................................................................................................................................13

10.2 Workplace monitoring ......... ..........................................................................................................................................................14

10.3 Individual monitoring ....................................................................................................................................................................14

11 Confirmatory monitoring programmes .....................................................................................................................................15

11.1 General aspects ....................................................................................................................................................................................15

11.2 Workplace monitoring ......... ..........................................................................................................................................................15

11.3 Individual monitoring ....................................................................................................................................................................15

12 Measurement techniques and performance criteria ...................................................................................................15

12.1 General ........................................................................................................................................................................................................15

12.2 Measurements performed in a laboratory specialised for radiobioassay ........................................16

12.2.1 In vitro...................................................................................................................................................................................16

12.2.2 In vivo ....................................................................................................................................................................................16

12.2.3 Quality assurance and quality control for bioassay laboratories .......................................16

12.3 Measurements performed in nuclear medicine service ...................................................................................17

13 Procedure for the assessment of exposures .........................................................................................................................17

13.1 Interpretation of individual monitoring data for dose assessment .......................................................17

13.1.1 General...................................................................................................................................................................................17

13.1.2 Dose assessment based on routine monitoring .................................................................................17

13.1.3 Dose assessment based on special monitoring ..................................................................................17

13.2 Software tools .......................................................................................................................................................................................22

13.3 Uncertainties .........................................................................................................................................................................................22

13.4 Quality assurance of the assessment process ...........................................................................................................22

14 Reporting and documentation ............................................................................................................................................................23

© ISO 2016 – All rights reserved iii
---------------------- Page: 9 ----------------------
SIST EN ISO 16637:2019
ISO 16637:2016(E)

14.1 Reporting results for in vitro measurements ...........................................................................................................23

14.2 Reporting results for in vivo measurements .............................................................................................................23

14.3 Documentation of the dose assessment .........................................................................................................................24

Annex A (informative) IAEA Safety Guide RS-G-1.2 “decision factor” ..............................................................................25

Bibliography .............................................................................................................................................................................................................................27

iv © ISO 2016 – All rights reserved
---------------------- Page: 10 ----------------------
SIST EN ISO 16637:2019
ISO 16637:2016(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 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.
© ISO 2016 – All rights reserved v
---------------------- Page: 11 ----------------------
SIST EN ISO 16637:2019
ISO 16637:2016(E)
Introduction

In the course of employment, individuals might 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 activity

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 the legislation, the purpose of the radiation protection programme, the probabilities of potential

radionuclide intakes, and the characteristics of the materials handled.

For these reasons, ISO standards establishing requirements for monitoring programmes (ISO 20553),

laboratory requirements (ISO 28218), and dose assessment (ISO 27048) have been developed. These can

be applied in a straightforward manner to many workplaces where internal contamination may occur.

In order to apply these standards to staff involved in diagnostic or therapeutic uses of radionuclides

in medicine, the short effective half-life of radionuclides commonly used for these purposes and the

distance between nuclear medicine department and in vivo counting facilities or radio-analytical

laboratories shall be taken into account. Consequently, guidance on the application of the three

International Standards cited above to nuclear medicine staff was requested by a number of countries.

This International Standard establishes criteria to determine whether intake monitoring is required

for staff exposed to medical radionuclides as unsealed sources. It also establishes requirements on the

design of such monitoring programmes, associated dose assessments, and laboratory requirements.

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 exchange of information

between authorities, supervisory institutions, and employers. This International Standard is not a

substitute for legal requirements.
vi © ISO 2016 – All rights reserved
---------------------- Page: 12 ----------------------
SIST EN ISO 16637:2019
INTERNATIONAL STANDARD ISO 16637:2016(E)
Radiological protection — Monitoring and internal
dosimetry for staff members exposed to medical
radionuclides as unsealed sources
1 Scope

This International Standard specifies the minimum requirements for the design of professional

programmes to monitor workers exposed to the risk of internal contamination via inhalation by

the use of radionuclides as unsealed sources in nuclear medicine imaging and therapy departments.

It establishes principles for the development of compatible goals and requirements for monitoring

programmes and, when adequate, dose assessment. It presents procedures and assumptions for the risk

analysis, for the monitoring programmes, and for the standardized interpretation of monitoring data.

This International Standard addresses 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 individual 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.
This International Standard does not address the following:

— monitoring and internal dosimetry for the workers exposed to laboratory use of radionuclides such

as radioimmunoassay techniques;

— monitoring and internal dosimetry for the workers involved in the operation, maintenance, and

servicing of PET cyclotrons;
— detailed descriptions of measuring methods and techniques;
— dosimetry for litigation cases;
— modelling for the improvement of internal dosimetry;
© ISO 2016 – All rights reserved 1
---------------------- Page: 13 ----------------------
SIST EN ISO 16637:2019
ISO 16637:2016(E)
— the potential influence of medical treatment of the internal contamination;
— the investigation of the causes or implications of an exposure;
— 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 20553, Radiation protection — Monitoring of workers occupationally exposed to a risk of internal

contamination with radioactive material

ISO 27048:2011, Radiation protection — Dose assessment for the monitoring of workers for internal

radiation exposure
ISO 28218, Radiation protection — Performance criteria for radiobioassay

ISO/IEC Guide 99, International vocabulary of metrology — Basic and general concepts and associated

terms (VIM)
3 Terms and definitions

For the purposes of this document, the terms and definitions given in ISO/IEC Guide 99, ISO 20553,

ISO 28218 and ISO 27048 and the following apply.
3.1
absorption

movement 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

3.2
absorption type F

as defined by ICRP, deposited materials that have high (fast) rates of absorption (3.1) into body fluids

from the respiratory tract
3.3
absorption type M

as defined by ICRP, deposited materials that have intermediate (moderate) rates of absorption (3.1) into

body fluids from the respiratory tract
3.4
activity
number of spontaneous nuclear transformations per unit time

Note 1 to entry: The activity is stated in becquerel (Bq), i.e. the number of transformations per second.

3.5
activity median aerodynamic diameter
AMAD

value of aerodynamic diameter such that 50 % of the airborne activity (3.4) in a specified aerosol is

associated with particles smaller than the AMAD, and 50 % of the activity is associated with particles

larger than the AMAD

Note 1 to entry: The aerodynamic diameter of an airborne particle is the diameter that a sphere of unit density

would need to have in order to have the same terminal velocity when settling in air as the particle of interest.

2 © ISO 2016 – All rights reserved
---------------------- Page: 14 ----------------------
SIST EN ISO 16637:2019
ISO 16637:2016(E)
3.6
contamination

activity (3.4) of radionuclides present on surfaces, or within solids, liquids or gases (including the

human body), where the presence of such radioactive material is unintended or undesirable

3.7
decision threshold

fixed value of the measurand by which, when exceeded by the result of an actual measurement of a

measurand quantifying a physical effect, it is decided that the physical effect is present

3.8
detection limit
smallest true value of the measurand which is detectable by the measuring method
3.9
annual dose

committed effective dose (3.11) resulting from all intakes (3.14) occurring during a calendar year

Note 1 to entry: The term “annual dose” is not used to represent the dose received in a year from all preceding

intakes.
3.10
committed equivalent dose

sum of the products of the total doses absorbed by an organ or a tissue from radiation types, integrated

over the commitment period following the intake (3.14) of a radionuclide, and the appropriate radiation

weighting factors
3.11
committed effective dose

sum of the products of the committed organ or tissue equivalent doses and the appropriate tissue

weighting factors

Note 1 to entry: In the context of this International Standard, the commitment period [integration time following

the intake (3.14)] is taken to be 50 years.
3.12
excretion function

function describing the fraction of an intake (3.14) excreted per day after a given time has elapsed since

the intake occurred
3.13
event = incident

any unintended occurrence, including operating error, equipment failure or other mishap, the

consequences or potential consequences of which are not negligible from the point of view of protection

or safety
3.14
intake

activity (3.4) of a radionuclide taken into the body in a given time period or as a result of a given event

3.15
in vitro analyses
indirect measurements

analyses including measurements of radioactivity present in biological samples taken from an

individual

Note 1 to entry: These include urine, faeces, and nasal samples; in special monitoring programmes (3.21), samples

of other materials, such as blood and hair, may be taken.
© ISO 2016 – All rights reserved 3
---------------------- Page: 15 ----------------------
SIST EN ISO 16637:2019
ISO 16637:2016(E)
3.16
in vivo measurements
direct measurements

measurement of radioactivity present in the human body, carried out using detectors to measure the

radiation emitted

Note 1 to entry: Normally, the measurement devices are whole-body or partial-body (e.g. lung, thyroid) counters.

3.17
monitoring

measurements made for the purpose of assessment or control of exposure to radioactive material and

the interpretation of the results

Note 1 to entry: This International Standard distinguishes five different categories of monitoring programmes,

namely, routine monitoring programme (3.18), task-related monitoring programme (3.19), triage monitoring

programme (3.20), special monitoring programme (3.21), and confirmatory monitoring programme (3.22).

Note 2 to entry: This International Standard distinguishes two different types of monitoring, namely, individual

monitoring (3.23) and workplace monitoring (3.24).
3.18
routine monitoring programme

monitoring programme associated with continuing operations and intended to demonstrate that

working conditions, including the levels of individual dose, remain satisfactory, and to meet regulatory

requirements
3.19
task-related monitoring programme

monitoring programme related to a specific operation, to provide information on a specific operation of

limited duration, or following major modifications applied to the installations or operating procedures,

or to confirm that the routine monitoring programme (3.18) is suitable
3.20
triage monitoring programme

monitoring programme consist of frequent measurements performed in the nuclear medicine centres

that does not enable one to calculate a dose but to verify that a given threshold of potential inta

...

Questions, Comments and Discussion

Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.