SIST EN ISO 6980-3:2025

SLOVENSKI STANDARD
01-december-2025
Jedrska energija - Referenčno sevanje delcev beta - 3. del: Umerjanje površinskih
in osebnih dozimetrov ter določanje njihovega odziva kot funkcije energije sevanja
beta in vpadnega kota (ISO 6980-3:2023)
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 6980-3:2023)
Énergie nucléaire - Rayonnement bêta de référence - Partie 3: Étalonnage des
dosimètres individuels et des dosimètres de zone et détermination de leur réponse en
fonction de l'énergie des particules bêta et de l'angle d'incidence du rayonnement bêta
(ISO 6980-3:2023)
Ta slovenski standard je istoveten z: EN ISO 6980-3:2025
ICS:
17.240 Merjenje sevanja Radiation measurements
27.120.01 Jedrska energija na splošno Nuclear energy in general
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

EN ISO 6980-3
EUROPEAN STANDARD
NORME EUROPÉENNE
September 2025
EUROPÄISCHE NORM
ICS 17.240
English Version
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 6980-3:2023)
Énergie nucléaire - Rayonnement bêta de référence -
Partie 3: Étalonnage des dosimètres individuels et des
dosimètres de zone et détermination de leur réponse
en fonction de l'énergie des particules bêta et de l'angle
d'incidence du rayonnement bêta (ISO 6980-3:2023)
This European Standard was approved by CEN on 22 September 2025.

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.

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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
© 2025 CEN All rights of exploitation in any form and by any means reserved Ref. No. EN ISO 6980-3:2025 E
worldwide for CEN national Members.

Contents Page
European foreword . 3

European foreword
The text of ISO 6980-3:2023 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 6980-3:2025 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 March 2026, and conflicting national standards shall
be withdrawn at the latest by March 2026.
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.
Any feedback and questions on this document should be directed to the users’ national standards body.
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 6980-3:2023 has been approved by CEN as EN ISO 6980-3:2025 without any
modification.
INTERNATIONAL ISO
STANDARD 6980-3
Third edition
2023-11
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
Énergie nucléaire — Rayonnement bêta de référence —
Partie 3: Étalonnage des dosimètres individuels et des dosimètres de
zone et détermination de leur réponse en fonction de l'énergie des
particules bêta et de l'angle d'incidence du rayonnement bêta
Reference number
ISO 6980-3:2023(E)
ISO 6980-3:2023(E)
© ISO 2023
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 6980-3:2023(E)
Contents Page
Foreword .iv
Introduction .v
1 Scope . 1
2 Normative references . 1
3 Terms and definitions . 1
4 Symbols and abbreviated terms, and reference and standard test conditions .3
5 Procedures applicable to all area and personal dosemeters . 4
5.1 General principles . 4
5.1.1 Selection of sources and radiation qualities . 4
5.1.2 Reference absorbed dose rate . 4
5.1.3 Conversion coefficients . 5
5.1.4 Reference conditions and standard test conditions . 5
5.1.5 Variation of influence quantities . . 5
5.1.6 Point of test and reference point . 6
5.1.7 Axes of rotation . 6
5.1.8 Condition of the dosemeter to be calibrated . 6
5.1.9 Influence of photon contribution . 6
5.2 Determination of calibration and correction factors . 6
5.2.1 Determination of the reference dose rate by a standard instrument . 6
5.2.2 Determination of reference calibration factor and correction factor for
non-linear response . 7
5.2.3 Determination of the correction factor for beta-particle energy and angle
of incidence, k . 7
E,α
6 Procedures for area dosemeters .8
6.1 General principles . 8
6.2 Quantity to be measured . 8
7 Procedures for personal dosemeters . 8
7.1 General principles . 8
7.2 Quantity to be measured . 8
7.3 Experimental conditions . 8
7.3.1 Use of phantoms . 8
7.3.2 Geometrical considerations in divergent beams . 9
7.3.3 Simultaneous irradiation of several dosemeters . . 9
8 Uncertainties .10
9 Reporting of results according to ISO 17025 .10
Annex A (normative) Reference conditions and standard test conditions .11
Annex B (informative) Conversion coefficients for some beta reference radiation fields .13
Bibliography .19
iii
ISO 6980-3:2023(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 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
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expressions related to conformity assessment, as well as information about ISO's adherence to
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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.
This third edition of ISO 6980-3 cancels and replaces ISO 6980-3:2022, of which it constitutes a minor
revision.
The main changes are the following:
— editorial changes throughout the document.
A list of all the parts in the ISO 6980 series can be found on the ISO website.
Any feedback or questions on this document should be directed to the user’s national standards body. A
complete listing of these bodies can be found at www.iso.org/members.html.
iv
ISO 6980-3:2023(E)
Introduction
ISO 6980 series covers the production, calibration, and use of beta-particle reference radiation fields
for the calibration of dosemeters and dose-rate meters for protection purposes. This document
describes procedures for the calibration of dosemeters and dose-rate meters and the determination
of their response as a function of beta-particle energy and angle of beta-particle incidence. ISO 6980-1
describes the methods of production and characterization of the reference radiation. ISO 6980-2
describes procedures for the determination of absorbed dose rate at a reference depth of tissue from
beta particle reference radiation fields.
For beta particles, the calibration and the determination of the response of dosemeters and dose-rate
meters is essentially a three-step process. First, the basic field quantity, absorbed dose to tissue at
a depth of 0,07 mm (and optionally also at a depth of 3 mm) in a tissue-equivalent slab geometry is
measured at the point of test, using methods described in ISO 6980-2. Then, the appropriate operational
quantity is derived by the application of a conversion coefficient that relates the quantity measured
(reference absorbed dose) to the selected operational quantity for the selected irradiation geometry.
Finally, the reference point of the device under test is placed at the point of test for the calibration
and determination of the response of the dosemeter. Depending on the type of dosemeter under test,
the irradiation is either carried out on a phantom or free-in-air for personal and area dosemeters,
respectively. For individual and area monitoring, this document describes the methods and the
conversion coefficients to be used for the determination of the response of dosemeters and dose-rate
meters in terms of the ICRU operational quantities, i.e., directional dose equivalent, H′(0,07;Ω) and
H′(3;Ω), as well as personal dose equivalent, H (0,07) and H (3).
p p
v
INTERNATIONAL STANDARD ISO 6980-3:2023(E)
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
1 Scope
This document describes procedures for calibrating and determining the response of dosemeters and
dose-rate meters in terms of the operational quantities for radiation protection purposes defined by the
[2]
International Commission on Radiation Units and Measurements (ICRU). However, as noted in ICRU 56 ,
the ambient dose equivalent, H*(10), used for area monitoring, and the personal dose equivalent, H (10),
p
as used for individual monitoring, of strongly penetrating radiation, are not appropriate quantities for
any beta radiation, even that which penetrates 10 mm of tissue (E > 2 MeV).
max
This document is a guide for those who calibrate protection-level dosemeters and dose-rate meters
with beta-reference radiation and determine their response as a function of beta-particle energy and
angle of incidence. Such measurements can represent part of a type test during the course of which
the effect of other influence quantities on the response is examined. This document does not cover the
in-situ calibration of fixed, installed area dosemeters. The term “dosemeter” is used as a generic term
denoting any dose or dose-rate meter for individual or area monitoring. In addition to the description
of calibration procedures, this document includes recommendations for appropriate phantoms and
the way to determine appropriate conversion coefficients. Guidance is provided on the statement of
measurement uncertainties and the preparation of calibration records and certificates.
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 6980-1, Nuclear energy — Reference beta-particle radiations — 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/IEC 17025:2017, General requirements for the competence of testing and calibration laboratories
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)
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 29661, ISO/IEC Guide 99 and
the following apply.
ISO 6980-3:2023(E)
ISO and IEC maintain terminological databases for use in standardization at the following addresses:
— ISO Online browsing platform: available at https:// www .iso .org/ obp
— IEC Electropedia: available at https:// www .electropedia .org/
3.1
maximum beta energy
E
max
highest value of the energy of beta particles emitted by a particular radionuclide which can emit one or
several continuous spectra of beta particles with different maximum energies
3.2
mean beta energy
E
mean
fluence averaged energy of the beta particle spectrum at the calibration distance free in air
3.3
residual maximum beta energy
E
res
highest value of the energy of a beta particle spectrum at the calibration distance, after having been
modified by scattering and absorption
3.4
reference absorbed dose
D
R
absorbed dose to tissue, D (0,07), in a slab phantom made of ICRU 4-element tissue with an orientation
t
of the phantom in which the normal to the phantom surface coincides with the (mean) direction of the
incident radiation
[4]
Note 1 to entry: The absorbed dose to tissue, D (0,07), is defined in ICRU 51 as personal absorbed dose, D (0,07).
t p
For the purposes of this document, this definition is extended to a slab phantom.
Note 2 to entry: It is considered that the rear part of the extrapolation chamber approximates a slab phantom
with sufficient accuracy by the material surrounding the standard instrument (extrapolation chamber) used for
[7][8]
the measurement of the beta radiation field .
Note 3 to entry: H (0,07) is obtained by the multiplication of the absorbed dose to tissue at 0,07 mm depth,
p
-1
D (0,07) = D , with the conversion coefficient 1 Sv Gy , see 5.2.2.2, Formula (3).
t R
3.5
reference beta-particle absorbed dose
D
Rβ
reference absorbed dose, D , (3.4) at a depth of 0,07 mm only due to beta particles
R
Note 1 to entry: As a first approximation, the ratio D /D is given by the bremsstrahlung correction k
Rβ R br
(see ISO 6980-2:2023, C.3).
3.6
reference calibration factor
N
calibration factor for a reference value, H , of the quantity to be measured. With M being the indicated
t,0 r,0
value:
H
t,0
N =
M
r,0
Note 1 to entry: This definition is of special importance for dosemeters having a non-linear response.
ISO 6980-3:2023(E)
3.7
correction factor for beta-particle energy and angle of incidence
k
E,α
correction factor for mean beta energy, E, and mean angle, α, of beta particle incidence
Note 1 to entry: α represents the angle of incidence from the source. Due to the scattering of the electrons, the
electrons are incident at a wide range of angles and α can be considered a mean representation of the angles
of incidence of the electrons. α is the angle between the reference direction of the source and the direction of
incidence of radiation from the source.
4 Symbols and abbreviated terms, and reference and standard test conditions
A list of symbols and abbreviated terms is given in Table 1.
Table 1 — Symbols and abbreviated terms
Symbol Meaning Unit
α (mean) angle of beta-particle incidence under calibration conditions deg
Ω direction of the radius vector of the ICRU sphere deg
D absorbed dose Gy
D reference absorbed dose Gy
R
−1
Ḋ rate of reference absorbed dose Gy·h
R
D reference beta-particle absorbed dose Gy
Rβ
−1
Ḋ reference beta-particle absorbed dose rate Gy·h
Rβ
E mean beta energy keV
mean
E maximum kinetic energy of a beta-particle spectrum keV
max
E residual maximum energy of a beta-particle spectrum keV
res
H dose equivalent Sv
H*(10) ambient dose equivalent Sv
−1
Ḣ*(10) rate of ambient dose equivalent Sv·h
H′(0,07;Ω) directional dose equivalent at 0,07 mm depth measured in the direction Ω Sv
−1
Ḣ'(0,07;Ω) rate of directional dose equivalent at 0,07 mm depth measured in the direction Ω Sv·h
H′(3;Ω) directional dose equivalent at 3 mm depth measured in the direction Ω Sv
−1
Ḣ'(3;Ω) rate of directional dose equivalent at 3 mm depth measured in the direction Ω Sv·h
H (0,07) personal dose equivalent at 0,07 mm depth Sv
p
H (3) personal dose equivalent at 3 mm depth Sv
p
−1
h absorbed-dose-to-dose-equivalent conversion coefficient from D to H Sv Gy
D R
−1
h′ (0,07;E,α) conversion coefficient from D to H′(0,07) for angle, α, and energy, E Sv Gy
D R
−1
h (0,07;E,α) conversion coefficient from D to H (0,07) for angle, α, and energy, E Sv Gy
p,D R p
−1
h′ (3;E,α) conversion coefficient from D to H′(3) for angle, α, and energy, E Sv Gy
D R
−1
h (3;E,α) conversion coefficient from D to H (3) for angle, α, and energy, E Sv Gy
p,D R p
H conventional true value of H Sv
t
H conventional true value of H in the reference conditions Sv
t,0
H' conventional true value of directional dose equivalent Sv
t
H' (0,07;Ω) conventional true value of directional dose equivalent at 0,07 mm depth measured Sv
t
in the direction Ω
H' (3;Ω) conventional true value of directional dose equivalent at 3 mm depth measured in Sv
t
the direction Ω
H conventional true value of the personal dose equivalent Sv
p,t
H (0,07) conventional true value of the personal dose equivalent at 0,07 mm depth Sv
p,t
ISO 6980-3:2023(E)
TTabablele 1 1 ((ccoonnttiinnueuedd))
Symbol Meaning Unit
H (3) conventional true value of the personal dose equivalent at 3 mm depth Sv
p,t
k correction factor for non-linear response —
n
k correction factor for beta-particle energy and angle of incidence —
E,α
M indicated value Sv
M indicated value under reference conditions Sv
r
M indicated value under reference conditions for a reference value of H Sv
r,0
N calibration factor —
N reference calibration factor —
R response —
The reference conditions as well as the standard test conditions are as given in Annex A.
5 Procedures applicable to all area and personal dosemeters
5.1 General principles
5.1.1 Selection of sources and radiation qualities
Two series of reference radiation sources are specified in ISO 6980-1. The series 1 sources use beam-
flattening filters to produce a uniform dose rate over an area of about 15 cm in diameter, e.g. for the
calibration of an area monitor or a number of personal dosemeters simultaneously. The calibration
distances, filter distances and filter types are specified in and shall be performed in accordance with
ISO 6980-1. Deviations from those specifications shall not be made.
Series 2 reference radiation may be produced without the use of beam-flattening filters and have the
advantage of extending the energy and dose rate beyond those of series 1. Calibrations and response
determinations shall specify the series of reference radiation used and the source-to-detector distance.
Although special sources and geometries may be established for beta calibrations, secondary
90 90
laboratories shall, as a minimum, have available a series 1 Sr/ Y source. These standard sources
provide consistent and reproducible results, permitting comparison of results from laboratory to
laboratory.
The dosimetry in these radiation fields shall be conducted in accordance with ISO 6980-2.
106 106
The beta radiation field produced by all these radionuclides except Ru/ Rh is practically free of
photon radiation, apart from bremsstrahlung generated in the surrounding materials or in the beta
106 106
particle source itself. Ru/ Rh is used because of the high maximum energy of the emitted beta
particles. Only beta-particle sources with small self-absorption and thin encapsulation can fulfil the
specifications in ISO 6980-1, since it is necessary that the maximum energy of the beta particles at the
calibration distance, E (residual maximum beta energy), be higher than a specified E value.
res res
5.1.2 Reference absorbed dose rate
The basic quantity in beta dosimetry, i.e., the absorbed-dose rate to tissue due to beta particles, Ḋ is
Rβ
determined in accordance with ISO 6980-2:2023, 7.2. From this, the reference absorbed dose rate, Ḋ , is
R
derived (see also ISO 6980-2:2023, 3.11 and 3.12) as given by Formula (1):

D
Rß

D = (1)
R
k
br
ISO 6980-3:2023(E)
5.1.3 Conversion coefficients
5.1.3.1 General dose equivalent quantities
According to ISO 29661:2012, 3.2.2, it is necessary to calculate the dose equivalent, H(d; source;α), where
H is equivalent to H′ and H and d is the depth 0,07 mm or 3 mm for beta radiation, from the reference
p
absorbed dose, D , using the absorbed-dose-to-dose-equivalent conversion coefficient, h (d; source;α).
R D
It is necessary to measure the reference absorbed dose, D , in a slab phantom at a depth of 0,07 mm and
R
at an incidence angle, α, of 0° between the source and the reference orientation of the slab phantom at
the distance of the point of test. Due to the scattering of the beta particles in air and within optional
beam-flattening filters, all real beta fields are far from unidirectional. Therefore, the above-mentioned
angle, α, is only the mean angle of an unknown distribution.
It is necessary to determine h (d; source;α) separately for any radiation field (given by the type of
D
radiation sources, the holder and the surrounding structures) and for any distance. The value of
h (d; source;α) depends also on the phantom used.
D
It is, therefore, not possible to give a generally applicable table of conversion coefficients. Measurements
and/or radiation transport simulations are necessary for any type of radiation field.
5.1.3.2 Determination of conversion coefficients
The determination of the conversion coefficients h (d; source;α) for the slab phantom can be done with
pD
the same instrument used for the measurement of the reference absorbed dose, D . For other phantoms
R
and other quantities, the most up to date method is Monte Carlo particle transport simulation. As an
[5][6]
example, the beta reference radiation fields from the beta secondary standard 2, BSS 2 , have been
[3]
determined and are freely available . Also, values of conversion coefficients h (d; source;α) have been
D
determined for the beta-particle radiation fields of the BSS 2 for the quantities H (0,07) –for the slab
p
and the rod phantom–, for the quantity H (3) – for the cylinder phantom–, as well as for the quantities
p
[4]
H'(0,07;Ω) and H'(3;Ω), all for different angles of incidence α . They are given in Annex B.
5.1.3.3 Phantom dependence
[7]
ISO 4037-3 specifies four types of phantoms: the ISO water-slab phantom, the ISO water-cylinder
phantom, the ISO water-pillar phantom and the ISO polymethylmethacrylate (PMMA)-rod phantom.
Contrary to photon and neutron radiation, the size and shape of the phantom have only a very small
influence on the beta radiation field in front of the phantom. However, the conventional quantity values,
and the associated conversion coefficients, slightly depend on the phantom. This is especially the case
for oblique radiation incidence where the differences can largely be attributed to the direct penetration
[4]
length to the measurement point . The conversion coefficients for the slab phantom can be used for
the pillar phantom up to 60° angle of incidence. Doing so, however, leads to larger uncertainties which
shall be assessed when doing so.
5.1.4 Reference conditions and standard test conditions
Calibrations and the determination of response shall be conducted under standard test conditions in
accordance with Tables A.1 and A.2. The range of values of influence quantities within the standard test
conditions are given in Tables A.1 and A.2 for radiation-related and other parameters, respectively.
5.1.5 Variation of influence quantities
For
...