EN ISO 14146:2024

SLOVENSKI STANDARD
01-september-2024
Radiološka zaščita - Merila in meje učinkovitosti za periodično ovrednotenje
dozimetričnih storitev za zunanje sevanje (ISO 14146:2024)
Radiological protection - Criteria and performance limits for the periodic evaluation of
dosimetry services for external radiation (ISO 14146:2024)
Strahlenschutz - Kriterien und Mindestanforderungen bei der wiederkehrenden
Überprüfung von Dosismessstellen (ISO 14146:2024)
Radioprotection - Critères et limites de performance pour l'évaluation périodique des
services de dosimétrie (ISO 14146:2024)
Ta slovenski standard je istoveten z: EN ISO 14146:2024
ICS:
13.280 Varstvo pred sevanjem Radiation protection
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

EN ISO 14146
EUROPEAN STANDARD
NORME EUROPÉENNE
July 2024
EUROPÄISCHE NORM
ICS 13.280 Supersedes EN ISO 14146:2021
English Version
Radiological protection - Criteria and performance limits
for the periodic evaluation of dosimetry services for
external radiation (ISO 14146:2024)
Radioprotection - Critères et limites de performance Strahlenschutz - Kriterien und Mindestanforderungen
pour l'évaluation périodique des services de bei der wiederkehrenden Überprüfung von
dosimétrie pour le rayonnement externe (ISO Dosismessstellen (ISO 14146:2024)
14146:2024)
This European Standard was approved by CEN on 6 July 2024.

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, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, Netherlands, Norway,
Poland, Portugal, Republic of North Macedonia, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland, Türkiye 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
© 2024 CEN All rights of exploitation in any form and by any means reserved Ref. No. EN ISO 14146:2024 E
worldwide for CEN national Members.

Contents Page
European foreword . 3

European foreword
This document (EN ISO 14146:2024) has been prepared by Technical Committee ISO/TC 85 "Nuclear
energy, nuclear technologies, and radiological protection" in collaboration with 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 January 2025, and conflicting national standards shall
be withdrawn at the latest by January 2025.
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.
This document supersedes EN ISO 14146:2021.
Any feedback and questions on this document should be directed to the users’ national standards
body/national committee. A complete listing of these bodies can be found on the CEN website.
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, France, Germany, Greece, Hungary, Iceland,
Ireland, Italy, Latvia, Lithuania, Luxembourg, Malta, Netherlands, Norway, Poland, Portugal, Republic of
North Macedonia, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden, Switzerland, Türkiye and the
United Kingdom.
Endorsement notice
The text of ISO 14146:2024 has been approved by CEN as EN ISO 14146:2024 without any modification.

International
Standard
ISO 14146
Third edition
Radiological protection — Criteria
2024-07
and performance limits for the
periodic evaluation of dosimetry
services for external radiation
Radioprotection — Critères et limites de performance pour
l’évaluation périodique des services de dosimétrie pour le
rayonnement externe
Reference number
ISO 14146:2024(en) © ISO 2024
ISO 14146:2024(en)
© ISO 2024
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
Email: copyright@iso.org
Website: www.iso.org
Published in Switzerland
ii
ISO 14146:2024(en)
Contents Page
Foreword .iv
1 Scope . 1
2 Normative references . 2
3 Terms and definitions . 2
4 Quantities measured . 8
5 Frequency of evaluation. 8
6 Test conditions . 9
6.1 Standard test conditions and special handling conditions .9
6.2 Radiation qualities .9
6.3 Dose range .10
6.4 Irradiation of dosemeters .11
7 Performance limits . .11
7.1 Limits to the response .11
7.1.1 General requirements .11
7.1.2 Requirements at reference conditions . 12
7.2 Approval criterion . 12
8 Operational procedures .12
8.1 Evaluation sample size . 12
8.2 Evaluation procedure . 13
8.3 Evaluation sequence . 13
9 Test report . 14
Annex A (normative) Reference conditions and standard test conditions .15
Annex B (informative) Graphical illustrations of the performance limits . 17
Bibliography . 19

iii
ISO 14146:2024(en)
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 document 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 ISO/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 third edition cancels and replaces the second edition (ISO 14146:2018) which has been technically
revised.
The main changes are as follows:
— the addition and clarification of several definitions;
— the modification of the requirements to environmental dosemeters;
— the addition of a requirement at reference conditions.
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.

iv
International Standard ISO 14146:2024(en)
Radiological protection — Criteria and performance limits
for the periodic evaluation of dosimetry services for external
radiation
1 Scope
This document specifies the dosimetric and organizational criteria and the test procedures to be used
for the periodic verification of the performance of dosimetry services supplying personal and/or area, i.e.
workplace and/or environmental, dosemeters used for individual (personal) and/or area, i.e. workplace
and/or environmental monitoring.
NOTE The quality of a supplier of a dosimetry service depends on both the characteristics of the approved
1)
(type-tested) dosimetry system and the training and experience of the staff, together with the calibration procedures
and quality assurance programmes.
The performance evaluation according to this document can be carried out by a dosimetry service to
demonstrate the fulfilment of specified performance requirements. The irradiation qualities used in this
document are representative for exposure situations that are expected or mimic workplace fields from the
radiological activities being monitored using the dosemeters from the services.
This document applies to personal and area dosemeters for the assessment of external photon radiation
with a fluence-weighted mean energy between 8 keV and 10 MeV, beta radiation with a fluence-weighted
mean energy between 60 keV and 1,2 MeV, and neutron radiation with a fluence-weighted mean energy
between 25,3 meV, i.e. thermal neutrons with a Maxwellian energy distribution with kT = 25,3 meV,
and 200 MeV.
It covers all types of personal and area dosemeters needing laboratory processing (e.g. thermoluminescent,
optically stimulated luminescence, radiophotoluminescent, track detectors or photographic-film
dosemeters) and involving continuous measurements or measurements repeated regularly at fixed time
intervals (e.g. several weeks, one month).
Active direct reading as well as semi-passive or hybrid dosemeters, such as direct ion storage (DIS) or silicon
photomultiplier (SiPM) dosemeters, for dose measurement, can also be treated according to this document.
Then, they are treated as if they were passive, i.e. the dosimetry service reads their indicated values and
reports them to the evaluation organization.
In this document, the corrected indicated (corrected indication) value is the one given by the dosimetry
systems as the final result of the evaluation algorithm (for example display of the software, printout) in
units of dose equivalent (Sv).
Environmental dosemeters usually indicate the quantity H*(10) but they can, in addition or alternatively,
indicate the quantity H'(3), H'(0,07), air kerma, K , or absorbed dose, D. All these dosemeters can also be
a
treated according to this document. If K or D is indicated (in Gy) the dose values in this document stated in
a
Sv shall then be interpreted as equivalent values in Gy.
1) If this document is applied to a dosimetry system for which no approval (pattern or type test) has been provided,
then in the following text approval or type test should be read as the technical data sheet provided by the manufacturer
or as the data sheet required by the regulatory body.

ISO 14146:2024(en)
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 4037-1, Radiological protection — X and gamma reference radiation for calibrating dosemeters and doserate
meters and for determining their response as a function of photon energy — Part 1: Radiation characteristics
and production methods
ISO 4037-2, Radiological protection — X and gamma reference radiation for calibrating dosemeters and
doserate meters and for determining their response as a function of photon energy — Part 2: Dosimetry for
radiation protection over the energy ranges from 8 keV to 1,3 MeV and 4 MeV to 9 MeV
ISO 4037-3, Radiological protection — X and gamma reference radiation for calibrating dosemeters and
doserate meters and for determining their response as a function of photon energy — Part 3: Calibration of area
and personal dosemeters and the measurement of their response as a function of energy and angle of incidence
ISO 6980-1, Nuclear energy — Reference beta-particle radiation — Part 1: Methods of production
ISO 6980-2, Nuclear energy — Reference beta-particle radiation — Part 2: Calibration fundamentals related to
basic quantities characterizing the radiation field
ISO 6980-3, Nuclear energy — Reference beta-particle radiation — Part 3: Calibration of area and personal
dosemeters and the determination of their response as a function of beta radiation energy and angle of incidence
ISO 8529-1, Neutron reference radiations fields — Part 1: Characteristics and methods of production
ISO 8529-2, Reference neutron radiations — Part 2: Calibration fundamentals of radiation protection devices
related to the basic quantities characterizing the radiation field
ISO 8529-3, Neutron reference radiation fields — Part 3: Calibration of area and personal dosemeters and
determination of their response as a function of neutron energy and angle of incidence
ISO 12749-2, Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 2:
Radiological protection
ISO 12789-1, Reference radiation fields — Simulated workplace neutron fields — Part 1: Characteristics and
methods of production
ISO 12789-2, Reference radiation fields — Simulated workplace neutron fields — Part 2: Calibration
fundamentals related to the basic quantities
ISO/IEC 17025, General requirements for the competence of testing and calibration laboratories
ISO/TS 18090-1, Radiological protection — Characteristics of reference pulsed radiation — Part 1: Photon
radiation
ISO 29661, Reference radiation fields for radiation protection — Definitions and fundamental concepts
ISO/IEC Guide 98-3, Uncertainty of measurement — Part 3: Guide to the expression of uncertainty in
me a s ur ement (GUM: 1995)
IEC 61267, Medical diagnostic X-ray equipment — Radiation conditions for use in the determination of
characteristics
3 Terms and definitions
For the purposes of this document, the terms and definitions given in ISO 12749-2, ISO 29661 and the
following apply.
ISO 14146:2024(en)
ISO and IEC maintain terminology databases for use in standardization at the following addresses:
— ISO Online browsing platform: available at https:// www .iso .org/ obp
— IEC Electropedia: available at https:// www .electropedia .org/
3.1
approved dosimetry system
dosimetry system that is used by a dosimetry service that has been approved or authorized for use by the
qualification body
Note 1 to entry: Several dosemeter designs can be operated using the same associated processing system (dosemeter
reader, etc.). Then, they are regarded as separate dosemeters/dosimetry systems.
3.2
area dosemeter
dosemeter designed to measure the ambient dose equivalent (rate) or the directional dose equivalent (rate)
Note 1 to entry: For a general definition of dosemeter, see 3.7.
Note 2 to entry: Area dosemeters are used for area monitoring which comprises environmental and workplace
monitoring, see 3.3.
[SOURCE: ISO 29661:2012, 3.1.2, modified — Notes 1 and 2 added.]
3.3
area monitoring
monitoring in which a workplace or an area in the environment is monitored by taking dose (rate)
measurements
Note 1 to entry: Area monitoring is usually performed in terms of H'(0,07), H'(3) or H*(10).
Note 2 to entry: Definition orientated at ICRP 103 and ICRP 116.
[SOURCE: IEC 62387:2020, 3.46]
3.4
background dose
radiation dose
dose (or an observed measure related to the dose) attributable to all sources other than the one(s) specified
Note 1 to entry: Strictly, this applies to measurements of dose or counts from a sample, where the background dose or
counts must be considered (usually subtracted) from all measurements. However, background is used more generally
to refer to the effects of other sources in any situation in which a particular source (or group of sources) is under
consideration. It is also applied to quantities other than doses, such as activity concentrations in environmental media.
Note 2 to entry: The background dose can contain dose fractions from transportation and/or other events such as
X-ray screening for security checks.
Note 3 to entry: To determine the background dose, usually, a group of control (background) dosemeters is used.
[SOURCE: IAEA Safety Glossary 2022, modified: “dose” and “(radiation dose)” added to the term; “dose rate”
removed; second sentence in note 1 rearranged; notes 2 and 3 added]
3.5
control dosemeter
personal, area or environmental dosemeter that provides an estimate of any radiation dose received by
the evaluation sample apart from that given by the irradiation laboratory or by a controlled exposure to
environmental radiation
Note 1 to entry: The control dosemeter provides a means of estimating and eliminating the contribution to the dose
from natural background radiation and that received during the time between zeroing and read out, i.e. the dose
during handling, transportation, etc.

ISO 14146:2024(en)
Note 2 to entry: The control dosemeters are used to determine the background radiation dose.
3.6
corrected indication
corrected indicated value
G
corr
indication of a dosemeter corrected for any differences of the values of the influence quantities from
reference conditions
Note 1 to entry: The corrected indication G can be calculated with the correction factor k for non-constant
corr n
response, the q correction factors, k , for the influence quantities of type F and the p correction summands, G , for the
f w
influence quantities of type S. It is given by
p q
Gk=⋅()GG−⋅ k
corr n ∑∏w f
w==11f
The equation above is a model function of the measurement necessary for any determination of the uncertainty
according to the ISO/IEC Guide 98-3 (GUM).
Note 2 to entry: Some dosimetry systems (3.9), especially such for neutron radiation, can have different correction
factors (or functions) k for different workplace categories w, each with its own reference radiation quality (e.g.
w
252 252
Cf(bare) for one workplace category and Cf(D O moderated) for another workplace category). Then, to obtain
the correspondingly corrected indicated dose value G , the uncorrected indicated values G, needs to be multiplied
corr
by k ≠ 1: G = G · k . Further information on the use of different correction factors (or functions) for different
w corr w
[2]
workplace categories can be found in ISO 21909-2 . In ISO 21909-2, the symbol for the correction factor (or function)
is k instead of k .
n,E,Ω w
[SOURCE: ISO 29661:2012, 3.1.11, modified — term “corrected indicated value” added and original Note 2
deleted and new Note 2 to entry added.]
3.7
dosemeter
device having a reproducible, measurable response to radiation that can be used to measure absorbed dose
(in Gy) or personal, ambient or directional dose equivalent (in Sv)
Note 1 to entry: In a wider sense, this term is used for meters designed to measure other quantities related to radiation
such as exposure, fluence, etc. Such use is deprecated.
Note 2 to entry: This apparatus may require a separate reader to read out and software to evaluate and display the
indicated value of the absorbed dose or dose equivalent.
Note 3 to entry: For specific types of dosemeters, see 3.2, 3.10, 3.17 and 3.25.
[SOURCE: ISO 12749-2:2022, 3.4.12, modified — “(in Gy)”, “(in Sv)” and “ambient or directional” added and
Notes 1 and 2 to entry added]
3.8
dosimetry service
organization that operates a personal, area and/or environmental dosimetry system which includes the
evaluation of the reading of dosemeters after their use and includes:
— providing the user with dosemeters;
— recording the results;
— reporting the results to the user.
Note 1 to entry: The dosimetry service fulfils basic quality management and independency requirements if it fulfils
the requirements stated in ISO/IEC 17025.

ISO 14146:2024(en)
Note 2 to entry: The user includes not only external clients but also internal personnel who wear dosemeters provided
by their own organization and are engaged in radiation protection activities inside or outside the organization. The
same quality of dosimetry service which is provided to external users is also provided to organizations' employees
(internal users), in accordance with their own quality management system.
3.9
dosimetry system
dosemeter, reader and all associated equipment and procedures including software used for assessing and
visualizing the indicated value
[SOURCE: IEC 62387:2020, 3.12, modified — “including software” and “and visualizing” added]
3.10
environmental dosemeter
dosemeter used for environmental monitoring
Note 1 to entry: For a general definition of environmental monitoring, see 3.11.
Note 2 to entry: Environmental dosemeters are typically used in areas of the environment close to or inside an
installation emitting ionizing radiations such as nuclear installations or medical accelerators. In these areas usually
no occupationally exposed person is present.
Note 3 to entry: Environmental dosemeters are generally used for monitoring the dose limits of the general
population, which are significantly lower as for occupationally exposed individuals. Consequently, the requirements
for environmental dosemeters are stronger than for workplace dosemeters, especially the lower dose limit of 35 µSv
and the extended range for the angle of incidence of the incident radiation ranging from 0° up to ±75°.
3.11
environmental monitoring
area monitoring (3.3) by the measurement of external dose (rate) in the environment
Note 1 to entry: Environmental monitoring is usually performed in terms of H'(0,07), H'(3) or H*(10).
[SOURCE: IEC 62387:2020, 3.48]
3.12
evaluation sample
randomly selected representative group of personal, area or environmental dosemeters used to evaluate the
performance of a dosimetry service (3.8)
Note 1 to entry: The evaluation sample includes dosemeters that are irradiated, remain unirradiated or serve as
control dosemeters for the evaluation procedure.
3.13
evaluation organization
impartial organization that administers the performance evaluation of dosimetry services (3.8) and assesses
the results
Note 1 to entry: The evaluation organization may include the irradiation laboratory.
Note 2 to entry: The evaluation organization fulfils basic quality management and independency requirements if it
fulfils the requirements stated in ISO/IEC 17043.
3.14
irradiation laboratory
impartial laboratory possessing radiation sources, calibration equipment and associated facilities traceable
to national, i.e. to primary or secondary, standards able to irradiate dosemeters from the evaluation sample
to a high degree of metrological accuracy
Note 1 to entry: The irradiation laboratory fulfils basic quality management and independency requirements if it
fulfils the requirements stated in ISO/IEC 17025 for calibration laboratories. Accreditation according to ISO/IEC 17025
impartially confirms the competence of the irradiation laboratory.

ISO 14146:2024(en)
3.15
indication
indicated value
G
quantity value provided by a measuring instrument or a measuring system
Note 1 to entry: The units of the indication of the dosemeter are not necessarily the same as that of the measurand. For
example, for measurements with ionization chambers the instrument indication is, in general, the value of the current
I or of the charge Q. It is necessary to document whether the indication is normalized to the reference conditions
to account for influence quantities and is corrected for intrinsic background and other influences. The corrected
indication is named G .
corr
Note 2 to entry: It may be necessary that a measured dose (e.g. by control dosemeters) or a transport and/or
background dose determined by other means be considered (usually subtracted) by the dosimetry service (3.8) or by
the evaluating organization, see notes to the definition of 3.18, irradiated dose.
Note 3 to entry: This definition means the same as “indicated value” in IEC 62387:2020, 3.14.
[SOURCE: ISO 29661:2012, 3.1.15, modified — term “indicated value” added and original Notes 1 and 3
deleted and new Notes 2 and 3 to entry added]
3.16
personal dosemeter
dosemeter used for individual (personal) monitoring
Note 1 to entry: For a general definition of dosemeter, see 3.7.
Note 2 to entry: Depending on the wearing position and type of construction a personal dosemeter may be a whole-
body dosemeter, an eye lens dosemeter or and extremity dosemeter.
Note 3 to entry: Personal dosemeters are used for individual monitoring, see 3.17.
3.17
individual monitoring
monitoring using dose (rate) measurements by equipment worn by individual workers
Note 1 to entry: Also called personal monitoring. Usually contrasted with workplace monitoring.
Note 2 to entry: Individual monitoring is performed in terms of H (0,07), H (3) or H (10).
p p p
[SOURCE: IEC 62387:2020, 3.49, modified — ”, or measurements of quantities of radioactive material in or on
their bodies” deleted in the end]
3.18
irradiated dose
H
ref
conventional quantity value of the dose to which the dosemeter (3.7) is irradiated
Note 1 to entry: In most cases, H is a dose irradiated by a calibration laboratory using artificial radiation sources
ref
(such as radionuclide sources, X-ray tubes or others) in addition to the background dose and, consequently, the
background dose must be considered (usually subtracted) to calculate the corrected indicated dose value G .
corr
Note 2 to entry: Especially for environmental dosemeters, H can include or be identical to a dose received from
ref
a controlled exposure to natural environmental radiation. In these cases, it is not considered (usually subtracted)
to calculate the corrected indicated dose value G . The conventional quantity value for natural environmental
corr
[3]
radiation can be assessed as described in the literature .
3.19
lower dose limit
H
dose below which irradiations should not be performed

ISO 14146:2024(en)
3.20
natural background dose
H
nat
doses or activity concentrations associated with natural sources or any other sources in the environment
that are not amenable to control
Note 1 to entry: This is normally considered to include doses or activity concentrations associated with natural
sources, global fallout (but not local fallout) from atmospheric nuclear weapon tests.
[SOURCE: IAEA Safety Glossary 2022, modified: “(radiation dose)” added to the term; “dose rate” removed]
3.21
qualification body
impartial organization empowered by a governmental, regulatory or advisory agency to approve a dosimetry
service (3.8) or authorize the use of a dosimetry system (3.9)
Note 1 to entry: The qualification body may include the evaluation organization (see 3.13).
Note 2 to entry: The qualification body fulfils basic quality management and independency requirements if it fulfils
the requirements stated in ISO/IEC 17025.
3.22
reference condition
operating condition prescribed for evaluating the performance of a measuring instrument or measuring
system or for comparison of measurement results
Note 1 to entry: Reference operating conditions specify intervals of values of the measurand and of the influence
quantities.
[SOURCE: JCGM. International vocabulary of metrology – Basic and general concepts and associated terms
rd
(VIM). 3 Ed. JCGM 200, 2012. p. 108]
Note 2 to entry: The term “reference condition” refers to an operating condition under which the specified instrumental
measurement uncertainty is the smallest possible.
[SOURCE: IEC 60050-300, 311-06-02]
Note 3 to entry: Reference conditions usually represent the set of influence quantities for which the calibration factor
is valid without any correction.
Note 4 to entry: The reference conditions for the quantity to be measured may be chosen freely in agreement with the
properties of the instrument under test. The quantity to be measured is not an influence quantity.
3.23
response
quotient of the indication, G, or of the corrected indication, G , divided by the conventional quantity value
corr
to be measured.
Note 1 to entry: The full specification of the response includes specification of whether it is determined from G or G
corr
and a statement of the measuring quantity. Examples are the response of the response of the corrected indication with
respect to the absorbed dose, R , and the response of the corrected indication with respect to the operational quantity
D
H (10), R .
p Hp(10)
Note 2 to entry: The reciprocal of the response at reference conditions is equal to the calibration coefficient.
Note 3 to entry: The value of the response may vary with the magnitude of the quantity to be measured (dose). In such
cases the response is said to be non-constant (or the indication is nonlinear).
Note 4 to entry: The response usually varies with the energy and directional distribution of the incident radiation.
Therefore, it may be useful to give the response as table of single values or diagram or curve or function R(E̅ ,Ω) of
the mean radiation energy E̅ of the radiation quality and the direction Ω of the incident monodirectional radiation.
R(E̅ ) describes the “energy dependence” and R(Ω) the “angular dependence” of the response; for the latter Ω may
be expressed by the angle, α, between the reference direction of the dosemeter and the direction of an external
monodirectional field.
ISO 14146:2024(en)
Note 5 to entry: For the determination of the photon energy dependence the most accurate information is obtained
experimentally if narrow spectra are used (e.g. for X-rays the radiation qualities of the N series as described in
ISO 4037-1).
[SOURCE: ISO 29661:2012, 3.1.34; “dose rate” removed; in Note 1 “the corrected indication with respect
to fluence, R , the response of the non-corrected indication with respect to kerma, R ,” deleted and Note 1
Φ K
extended by an example for H (10); Note 5: “photon” added and “small spectra” changed to “narrow spectra”]
p
3.24
upper dose limit
H
top
dose above which irradiations should not be performed
3.25
workplace dosemeter
dosemeter used for workplace monitoring
Note 1 to entry: For a general definition of workplace monitoring, see 3.26.
Note 2 to entry: Workplace dosemeters are typically used in areas where usually occupationally exposed persons are
present.
3.26
workplace monitoring
area monitoring (3.3) using dose (rate) measurements made in the working environment
Note 1 to entry: Usually contrasted with individual monitoring (3.17).
Note 2 to entry: Workplace monitoring is usually performed in terms of H'(0,07), H'(3) or H*(10).
[SOURCE: IEC 62387:2020, 3.47]
4 Quantities measured
The quantities measured in the evaluation shall be the personal dose equivalent H (10), H (3) or H (0,07),
p p p
the ambient dose equivalent H*(10) or the directional dose equivalent H'(3) or H'(0,07) as recommended by
[4] [5]
the ICRU in Report 47 and Report 51 . All irradiations for H (d) shall be performed on ISO phantoms in
p
accordance with the standard test conditions in Table A.1 of Annex A. When these phantoms are used, no
correction factors shall be applied to the indication of the dosemeter under test due to possible differences
in backscatter properties between these phantoms and the ICRU tissue phantoms.
5 Frequency of evaluation
As a general rule, performance evaluations should be repeated at regular intervals (e.g. every one or two
years), see ISO/IEC 17025:2017, 7.7. If any significant change of the dosimetry system or the dosimetry service
occurs after an evaluation which may change the performance of the dosimetry service and/or dosimetry
system, performing a new evaluation shall be considered. To maintain compliance with this document for a
specific dosimetry system, performance evaluations should be repeated regularly, at best every three years.
If a performance test is not provided within this period, four years are recommended, however, at maximum
five years is acceptable.
For approved dosimetry systems in countries where applicable, the qualification body shall be notified of
the results of the evaluations and of any significant change of the dosimetry service and/or in the dosimetry
system after approval. The qualification body shall recommend a new evaluation when it believes that the
modifications may change the performance of the dosimetry service and/or dosimetry system.

ISO 14146:2024(en)
6 Test conditions
6.1 Standard test conditions and special handling conditions
The dosimetry service shall supply complete dosemeter badges or holders, i.e. complete dosemeter package
as it would be worn by a monitored individual or posted as a workplace or environmental dosemeter. A badge
or holder consists of the radiation detector(s), possible supplemental filtering materials, labelling and/or
identification typically placed within an enclosure suitable for the conditions where it is used and equipped
with a means to attach the enclosure to the wearer or within the workplace/environment (e.g. a clip).
The dosimetry service shall
— clearly indicate the front face of the dosemeters, i.e. the face which shall face the radiation source,
— specify the reference point of the dosemeters, and
— provide information on the position (depth) of the sensitive element in the dosemeters.
Environmental dosemeters shall be waterproof.
According to an addition to 6.6.3 in ISO 29661:2012/Amd.1:2015, the reference point of a personal dosemeter
can be defined as the rear side of the dosemeter so that it coincides with a point on the front surface of the
phantom. Thus, the irradiation laboratory may choose the point of test at the dosemeter’s reference points
or, in case of personal dosemeters, the phantom front – as appropriate (see ISO 29661:2012/Amd.1:2015).
The dosimetry service shall not be aware of the radiation qualities and doses used for the irradiations.
One or more dosemeter can be irradiated per irradiation condition.
NOTE 1 One good practice for the irradiation laboratory is that different participants’ systems are irradiated at
the same time, i.e. using the same setup and/or simultaneously on the phantom. This enables cross checking in case of
potential irradiation errors.
In case several dosemeters are irradiated simultaneously, 6.6.5 of ISO 29661:2012 shall be obeyed.
Those quantities which may influence the result, such as ambient temperature, relative humidity,
background radiation and radioactive contamination, as well as further influence quantities not intended to
be varied shall conform to the standard test conditions as given in Annex A.
During the performance evaluation cycle, the evaluation sample, including the control dosemeters, shall
be stored in environmental conditions that do not affect the measurement results obtained from the
dosemeters. Alternative storage conditions may be used in order to mimic real conditions, especially for
environmental dosemeters.
For an accurate consideration (usually subtraction) of the background radiation dose from the readings of
the test dosemeters, the amount of time that the controls and test dosemeters are separated, i.e. the time that
it takes to perform the tests, shall be minimized. Ideally, the difference between the accumulated control
background and the natural background of the test dosemeters should be less than 0,01 mSv, or as small as
possible. In any case, it shall be smaller than half of the lower dose limit.
If more than one irradiation laboratory performs the irradiations, sufficient control dosemeters must be
provided by the dosimetry service in order to make sure that each group of dosemeters is accompanied by
sufficient control and spare dosemeters, see 8.1.
6.2 Radiation qualities
The radiation sources shall be chosen from those specified in ISO 4037-1 (reference photon radiation fields),
ISO 6980-1 (reference beta radiation fields), ISO 8529-1 (reference neutron radiation fields), ISO 12789-1
[simulated workplace fields with broad energy and angle distributions (e.g. isotropic)], or IEC 61267 (medical
diagnostic radiation fields) according to those radiation types for which the system has been approved. In
order to mimic real workplace conditions, other radiation fields may be used if qualified reference dose

ISO 14146:2024(en)
measurements are performed. Mixtures may also be used. Pulsed reference photon radiation fields shall be
chosen from those specified in ISO/TS 18090-1 or other specified radiation fields.
Additional reference fields of natural environmental radiation may be chosen, especia
...