EN ISO 29661:2017

Reference radiation fields for radiation protection - Definitions and fundamental concepts (ISO 29661:2012, including Amd 1:2015)

ISO 29661:2012 defines terms and fundamental concepts for the calibration of dosemeters and equipment used for the radiation protection dosimetry of external radiation -- in particular, for beta, neutron and photon radiation. It defines the measurement quantities for radiation protection dosemeters and doserate meters and gives recommendations for establishing these quantities. For individual monitoring, it covers whole body and extremity dosemeters (including those for the skin and the eye lens), and for area monitoring, portable and installed dosemeters. Guidelines are given for the calibration of dosemeters and doserate meters used for individual and area monitoring in reference radiation fields. Recommendations are made for the position of the reference point and the phantom to be used for personal dosemeters.
ISO 29661:2012 also deals with the determination of the response as a function of radiation quality and angle of radiation incidence.
ISO 29661:2012 is intended to be used by calibration laboratories and manufacturers.

Referenzstrahlungsfelder für den Strahlenschutz - Definitionen und grundlegende Konzepte (ISO 29661:2012, einschließlich Amd 1:2015)

Diese Internationale Norm definiert Begriffe und grundlegende Konzepte für die Kalibrierung von Dosimetern und Geräten, die für die Strahlenschutzdosimetrie von externer Strahlung – insbesondere für Beta-, Neutro-nen- und Photonenstrahlung – Verwendung finden. Sie definiert die Messgrößen für Strahlen¬schutzdosimeter zur Messung der Dosis und Dosisleistung und gibt Empfehlungen für die Darstellung dieser Messgrößen. Für die Personendosimetrie behandelt sie Ganzkörper- und Teilkörperdosimeter (einschließlich derjenigen für die Haut und die Augenlinse) und für die Ortsdosimetrie tragbare und fest installierte Dosimeter. Für die Kalibrie¬rung von Dosimetern zur Messung der Orts- und Personendosis und Orts- und Personendosisleistung in Referenzstrahlungsfeldern werden Leitfäden gegeben. Für Personendosimeter werden Empfehlungen für die Position des Bezugspunktes und für das zu verwendende Phantom gegeben.
Diese Internationale Norm behandelt ebenfalls die Bestimmung des Ansprechvermögens als Funktion der Strahlungsqualität und des Strahleneinfallswinkels.
Sie ist gedacht für die Anwendung in Kalibrierlaboratorien und bei Herstellern.

Champs de rayonnement de référence pour la radioprotection - Définitions et concepts fondamentaux (ISO 29661:2012, y compris Amd 1:2015)

L'ISO 29661:2012 définit des termes et des concepts fondamentaux pour l'étalonnage des dosimètres et pour l'équipement utilisé en dosimétrie de radioprotection pour l'exposition externe, en particulier pour les rayonnements bêta, neutroniques et photoniques. Elle définit les grandeurs de mesure pour les dosimètres et débitmètres de radioprotection et donne des recommandations pour l'établissement de ces grandeurs. Elle couvre, pour la surveillance individuelle, les dosimètres pour le corps entier et les dosimètres d'extrémités (y compris les dosimètres pour la peau et le cristallin), et pour la surveillance de zone, les dosimètres portatifs et installés. Des lignes directrices sont proposées pour l'étalonnage des dosimètres et des débitmètres utilisés pour la surveillance individuelle et la surveillance de zone dans des champs de rayonnement de référence. Des recommandations sont données pour la position du point de référence et le fantôme à utiliser pour les dosimètres individuels.
L'ISO 29661:2012 traite également de la détermination de la réponse en fonction de la qualité du rayonnement et de l'angle d'incidence du rayonnement.
Elle est destinée à fournir des conseils aux laboratoires d'étalonnage et aux fabricants.

Referenčna sevalna polja za zaščito pred sevanjem - Definicije in temeljni koncepti (ISO 29661:2012, vključno z dopolnilom Amd 1:2015)

Standard ISO 29661:2012 določa izraze in temeljne koncepte za umerjanje dozimetrov in opreme, ki se uporabljajo za dozimetrijo zaščite pred sevanjem pri zunanjem sevanju, še zlasti za beta, nevtronsko in fotonsko sevanje. Določa merilne količine za dozimetre za zaščito pred sevanjem in merilnike odmerkov ter podaja priporočila za določitev teh količin. Za nadzor posameznika zajema dozimetre za celo telo in okončine (vključno s tistimi za kožo in očesno lečo), za nadzor območja pa prenosne in nameščene dozimetre. Podane so smernice za umerjanje dozimetrov in merilnikov odmerkov, ki se uporabljajo za nadzor posameznika in območja na referenčnih območjih sevanja. Priporočila so podana za položaj referenčne točke in fantoma, ki se uporabljata za osebne dozimetre.
Standard ISO 29661:2012 opisuje tudi določanje odziva kot funkcije kakovosti sevanja in kota pojavnega sevanja.
Standard ISO 29661:2012 je namenjen za uporabo s strani laboratorijev za umerjanje in proizvajalcev.

General Information

• Status: Published
• Publication Date: 17-Oct-2017
• Withdrawal Date: 29-Apr-2018
• ICS: 13.280 - Radiation protection
• Technical Committee: CEN/TC 430 - Nuclear energy, nuclear technologies, and radiological protection
• Drafting Committee: CEN/TC 430 - Nuclear energy, nuclear technologies, and radiological protection
• Current Stage: 6060 - Definitive text made available (DAV) - Publishing
• Start Date: 18-Oct-2017
• Due Date: 05-May-2019
• Completion Date: 18-Oct-2017
• Ref Project: SIST EN ISO 29661:2018 - Reference radiation fields for radiation protection - Definitions and fundamental concepts (ISO 29661:2012)

Overview - EN ISO 29661:2017 / ISO 29661:2012 (Amd 1:2015)

EN ISO 29661:2017 (identical to ISO 29661:2012 including Amendment 1:2015) establishes the definitions and fundamental concepts for reference radiation fields used in radiation protection. The standard focuses on the calibration and characterization of dosemeters and doserate meters for external radiation (beta, neutron and photon). It defines the measurement and operational quantities used for individual (personal) monitoring and area monitoring, gives recommendations for establishing those quantities in reference radiation fields, and provides guidance on calibration practice and determination of instrument response.

Key topics and requirements

• Terms and definitions: Harmonized vocabulary for calibration, calibration coefficient, calibration factor, reference conditions, and response.
• Measurement quantities: Specification of operational quantities for area monitoring (e.g., ambient and directional dose equivalents) and for personal monitoring (whole body, extremity, skin and eye lens dose equivalents).
• Calibration in reference radiation fields: Guidance for calibrating dosemeters and doserate meters under defined reference conditions (including position of reference point and use of phantoms for personal dosemeters).
• Response characterization: Procedures to determine dosemeter response as a function of radiation quality (photon, beta, neutron) and angle of incidence.
• Calibration coefficient and correction: Definition and use of calibration coefficients and calibration factors to convert instrument indications to conventional quantities.
• Uncertainty and certification: Requirements for expressing measurement uncertainty and content of calibration certificates.
• Normative annexes: Reference conditions, standard test conditions and a description of calibration coefficient concepts.

Practical applications and users

• Calibration laboratories: Implement reference-field procedures to provide traceable calibrations for instruments used in radiation protection.
• Manufacturers of dosemeters and survey meters: Design, test and declare instrument performance across radiation qualities and angles of incidence.
• Radiation protection specialists: Establish measurement programs for workplace monitoring (area and personal).
• Regulatory bodies & accredited testing bodies: Use the standard to define compliance, accreditation criteria and calibration reporting requirements.

Practical benefits include improved comparability of calibrations, consistent expression of measurement uncertainty, and reliable assessment of personal and area dose in occupational and environmental radiation protection.

Related standards

• ISO 4037, ISO 6980, ISO 8529 and ISO 12789 - complementary standards that describe production and characterization of photon, beta and neutron reference radiation fields and dosimetry methods.
• ICRU reports referenced for operational quantity definitions.

Keywords: EN ISO 29661:2017, ISO 29661:2012, reference radiation fields, radiation protection, calibration of dosemeters, doserate meters, personal monitoring, area monitoring, calibration laboratories, manufacturers.

Standards Content (Sample)

SLOVENSKI STANDARD
01-februar-2018
5HIHUHQþQDVHYDOQDSROMD]D]DãþLWRSUHGVHYDQMHP'HILQLFLMHLQWHPHOMQLNRQFHSWL
,62YNOMXþQR]GRSROQLORP$PG
Reference radiation fields for radiation protection - Definitions and fundamental concepts
(ISO 29661:2012)
Champs de rayonnement de référence pour la radioprotection - Définitions et concepts
fondamentaux (ISO 29661:2012)
Ta slovenski standard je istoveten z: EN ISO 29661:2017
ICS:
13.280 Varstvo pred sevanjem Radiation protection
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

EN ISO 29661
EUROPEAN STANDARD
NORME EUROPÉENNE
October 2017
EUROPÄISCHE NORM
ICS 13.280
English Version
Reference radiation fields for radiation protection -
Definitions and fundamental concepts (ISO 29661:2012,
including Amd 1:2015)
Champs de rayonnement de référence pour la
radioprotection - Définitions et concepts
fondamentaux (ISO 29661:2012, y compris Amd
1:2015)
This European Standard was approved by CEN on 13 September 2017.

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: Avenue Marnix 17, B-1000 Brussels
© 2017 CEN All rights of exploitation in any form and by any means reserved Ref. No. EN ISO 29661:2017 E
worldwide for CEN national Members.

Contents Page
European foreword . 3

European foreword
The text of ISO 29661:2012, including Amd 1:2015 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 29661:2017 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 April 2018, and conflicting national standards shall be
withdrawn at the latest by April 2018.
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 29661:2012, including Amd 1:2015 has been approved by CEN as EN ISO 29661:2017
without any modification.
INTERNATIONAL ISO
STANDARD 29661
First edition
2012-09-01
Reference radiation fields for
radiation protection — Definitions and
fundamental concepts
Champs de rayonnement de référence pour la radioprotection —
Défintions et concepts fondamentaux
Reference number
ISO 29661:2012(E)
©
ISO 2012
ISO 29661:2012(E)
All rights reserved. Unless otherwise specified, no part of this publication may be reproduced or utilized in any form or by any means,
electronic or mechanical, including photocopying and microfilm, without permission in writing from either ISO at the address below or ISO’s
member body in the country of the requester.
ISO copyright office
Case postale 56 • CH-1211 Geneva 20
Tel. + 41 22 749 01 11
Fax + 41 22 749 09 47
E-mail [e-mail]
Web www.iso.org
Published in Switzerland
ii © ISO 2012 – All rights reserved

ISO 29661:2012(E)
Contents Page
Foreword .iv
Introduction . v
1 Scope . 1
2 Normative references . 1
3 Terms and definitions . 1
3.1 General . 1
3.2 Quantities and conversion coefficients . 9
4 Symbols .15
5 Application of the measurement quantities and units .17
5.1 Measurement quantities for area monitoring .17
5.2 Measurement quantities for individual monitoring .18
5.3 Establishing of the measurement quantities for area and individual monitoring .18
6 Calibration and determination of the response in reference radiation fields .18
6.1 General principles .18
6.2 Calibration in reference radiation fields .19
6.3 Determination of the response in reference radiation fields .21
6.4 Methods for the determination of the calibration coefficient .22
6.5 Special considerations for area dosemeters (area survey meters) .25
6.6 Special considerations for personal dosemeters .26
7 Uncertainty .29
8 Certificates .29
Annex A (normative) List of reference conditions and standard test conditions .30
Annex B (normative) Description of the calibration coefficient .31
Bibliography .33
ISO 29661:2012(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.
International Standards are drafted in accordance with the rules given in the ISO/IEC Directives, Part 2.
The main task of technical committees is to prepare International Standards. Draft International Standards
adopted by the technical committees are circulated to the member bodies for voting. Publication as an
International Standard requires approval by at least 75 % of the member bodies casting a vote.
Attention is drawn to the possibility that some of the elements of this document may be the subject of patent
rights. ISO shall not be held responsible for identifying any or all such patent rights.
ISO 29661 was prepared by Technical Committee ISO/TC 85, Nuclear energy, nuclear technologies, and
radiological protection, Subcommittee SC 2, Radiological protection.
iv © ISO 2012 – All rights reserved

ISO 29661:2012(E)
Introduction
[1].[12]
International Standards ISO 4037, ISO 6980, ISO 8529 and ISO 12789 , with focus on photon, beta and
neutron reference radiation fields, are each divided into several parts: one part gives the methods of production
and characterization of reference radiation fields, and others describe the dosimetry of the reference radiation
qualities and the procedures for calibrating and determining the response of dosemeters and doserate meters
in terms of the operational quantities of the International Commission on Radiation Units and Measurements
[25] [26] [27] [28] [31]
(ICRU) .
The subject of these four International Standards is the same; they differ only in the kind of radiation each
addresses. Their terms and definitions, and most of the descriptions of methods and procedures given are
basically the same — whatever the radiation. Nevertheless, they do differ, more or less, from one to the other
in detail. This International Standard brings together terms and definitions and fundamental concepts common
to all of them. Thus, it serves to harmonize International Standards on radiation protection.
Besides definitions relating to calibration primary quantities, the operational quantities for area and individual
monitoring are specified. For area monitoring, the operational quantities are ambient dose equivalent, H*(10),
 
directional dose equivalents,H'(0,07,Ω) and H'(3,)Ω , and the appropriate dose rates. For individual monitoring
using personal dosemeters, the dose equivalent quantities, H (10), H (0,07) and H (3), and the respective dose
p p p
rates are available.
The method used to represent these operational quantities is the following. First, a basic (primary) quantity, such
as air kerma free-in-air, fluence or absorbed dose to soft tissue, is measured. Then the appropriate operational
quantity is derived by the application of the conversion coefficient that relates the basic (primary) quantity to
the selected operational quantity. The procedure for the calibration and the determination of the response of
radiation protection dosemeters is described in general terms. Depending on the type of dosemeter under test,
the position of the reference point is specified differently and the irradiation is either carried out on a phantom
(for personal dosemeters) or free in air (for area dosemeters or area survey meters).
With the publication of this International Standard, it is intended that ISO 4037, ISO 6980, ISO 8529 and
ISO 12789 be revised successively for further harmonization since, among other aspects, certain of their
definitions differ from those published here and the symbols chosen for this International Standard are more
consistent with ICRU reports and other International Standards used for radiation protection purposes.
INTERNATIONAL STANDARD ISO 29661:2012(E)
Reference radiation fields for radiation protection — Definitions
and fundamental concepts
1 Scope
This International Standard defines terms and fundamental concepts for the calibration of dosemeters and
equipment used for the radiation protection dosimetry of external radiation — in particular, for beta, neutron
and photon radiation. It defines the measurement quantities for radiation protection dosemeters and doserate
meters and gives recommendations for establishing these quantities. For individual monitoring, it covers whole
body and extremity dosemeters (including those for the skin and the eye lens), and for area monitoring, portable
and installed dosemeters. Guidelines are given for the calibration of dosemeters and doserate meters used for
individual and area monitoring in reference radiation fields. Recommendations are made for the position of the
reference point and the phantom to be used for personal dosemeters.
This International Standard also deals with the determination of the response as a function of radiation quality
and angle of radiation incidence.
It is intended to be used by calibration laboratories and manufacturers.
2 Normative references
The following referenced documents are indispensable for the application of this document. For dated
references, only the edition cited applies. For undated references, the latest edition of the referenced document
(including any amendments) applies.
ISO/IEC Guide 98-3:2008, Uncertainty of measurement — Part 3: Guide to the expression of uncertainty in
measurement (GUM:1995)
ISO/IEC 17025:2005, General requirements for the competence of testing and calibration laboratories.
Corrected by ISO/IEC 17025:2005/Cor 1:2006
3 Terms and definitions
For the purposes of this document, the following terms and definitions apply.
NOTE These terms and definitions are relevant for the calibration of dosemeters and for the quantities and conversion
coefficients that are general to ISO 4037, ISO 6980, ISO 8529 and ISO 12789. Special terms and definitions can be found
in those International Standards.
3.1 General
3.1.1
angle of radiation incidence
α
angle, in the coordinate system of the dosemeter, between the direction of radiation incidence and the reference
direction of the dosemeter in unidirectional fields
3.1.2
area dosemeter
area survey meter
meter designed to measure the ambient dose equivalent (rate) or the directional dose equivalent (rate)
[SOURCE: IEV 394-22-08, modified.]
ISO 29661:2012(E)
3.1.3
background indication
indication obtained from a phenomenon, body or substance similar to the one under investigation, but for which
a quantity of interest is supposed not to be present, or is not contributing to the indication
[SOURCE: ISO/IEC Guide 99:2007, 4.2.]
3.1.4
calibration
operation that, under specified conditions, in a first step, establishes a relation between the quantity values
with measurement uncertainties provided by measurement standards and the corresponding indications with
associated measurement uncertainties and, in a second step, uses this information to establish a relation for
obtaining a measurement result from an indication
[SOURCE: ISO/IEC Guide 99:2007, 2.39.]
Note 1 to entry: A calibration may be expressed by a statement, calibration function, calibration diagram, calibration
curve, or calibration table. In some cases, it may consist of an additive or multiplicative correction of the indication with
associated measurement uncertainty.
Note 2 to entry: The measurement standard can be a primary standard, a secondary standard or a working
measurement standard.
Note 3 to entry: Often the first step alone in the above definition is perceived as being calibration.
3.1.5
calibration coefficient
N(U,α)
quotient of the conventional quantity value to be measured and the corrected indication of the dosemeter
normalized to reference conditions
Note 1 to entry: The calibration coefficient N(U,α) for the reference radiation quality U and the angle of incidence α is
equivalent to the calibration factor multiplied by the instrument coefficient (see Annex B). It is given by
H
o
N(,UUαα)(==Cc,)⋅ (1)
fi
G
corr
where
H is the conventional quantity value;
o
G is the corrected indication;
corr
C (U,α) is the calibration factor for the radiation quality U and the angle of incidence α; and
f
c is the instrument constant.
i
Concerning the dimension of the calibration factor and the calibration coefficient, see the Notes to 3.1.7 and 3.1.17.
Note 2 to entry: The reciprocal of the calibration coefficient is the response under reference conditions. The value of the
calibration factor may vary with the magnitude of the quantity to be measured. In such cases a dosemeter is said to have
a non-constant response (or a nonlinear indication).
Note 3 to entry: To distinguish between the indication of the standard and the dosemeter, subscripts ‘s’ and ‘d’ are used
and the respective coefficients are named N(U,α) and N(U,α) .
s d
[SOURCE: ICRU Report 76 modified.]
3.1.6
calibration conditions
conditions within the range of standard test conditions actually prevailing during the calibration measurement
2 © ISO 2012 – All rights reserved

ISO 29661:2012(E)
3.1.7
calibration factor
C (U,α)
f
factor by which the product of the corrected indication, G , and the associated instrument constant, c , of the
corr i
dosemeter is multiplied to obtain the conventional quantity value to be measured under reference conditions
Note to entry: The calibration factor is dimensionless.
[SOURCE: ICRU Report 76, modified.]
3.1.8
conventional quantity value
H
o
quantity value attributed by agreement to a quantity for a given purpose
Note to entry: The conventional quantity value H is the best estimate of the quantity to be measured, determined by a
o
primary standard or a secondary or working measurement standard which are traceable to a primary standard.
[SOURCE: ISO/IEC Guide 99:2007, 2.39.]
3.1.9
correction factor
k
numerical value by which the indication is multiplied to compensate for the deviation of measurement conditions
from reference conditions or for a systematic effect (e.g. ion recombination)
Note to entry: If the correction of the effect of an influence quantity requires a multiplicative factor, the influence quantity
is of type F, see Note to entry 1 for 3.1.16.
3.1.10
correction factor for non-constant response
k
n
numerical value by which the indication is multiplied to compensate for the non-constant response (or non-linear
indication) of the dosemeter, i.e. for the variation of the calibration factor or calibration coefficient with the
variation of the magnitude of the quantity to be measured
Note to entry: For a dosemeter with constant response with respect to the selected measuring quantity, k is equal to unity.
n
3.1.11
corrected indication
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 (2)
corr n w f
∑ ∏
w=1 f=1
which is a model function of the measurement necessary for any determination of the uncertainty according to
ISO/IEC Guide 98-3.
Note 2 to entry: To distinguish between the indication of the standard and the dosemeter, Subscripts ‘s’ and ‘d’ are used
and the respective indications are named G and G .
s,corr d,corr
ISO 29661:2012(E)
3.1.12
correction summand
G
w
value added to the indication to compensate the deviation of measurement conditions from reference conditions
or for a systematic error (e.g. zero indication)
Note to entry: If the correction of the effect of an influence quantity requires a summand, the influence quantity is of
type S, see Note 1 to entry 3.1.16.
3.1.13
ICRU tissue
−3
material equivalent to the human soft tissue with a density of 1 g·cm and a mass composition of 76,2 %
oxygen, 11,1 % carbon, 10,1 % hydrogen and 2,6 % nitrogen
[SOURCE: ICRU Report 33.]
3.1.14
ICRU sphere
spherical phantom of 30 cm in diameter made of ICRU tissue
Note to entry: This phantom is only used for the calculation of conversion coefficients to ambient or directional dose
equivalent and not for dosemeter calibration.
[SOURCE: ICRU Report 33, modified.]
3.1.15
indication
G
quantity value provided by a measuring instrument or a measuring system
Note 1 to entry: A measuring instrument or a measuring system may consist of several parts, e.g. the ionisation chamber
plus the electrometer, or the complete instrument in one housing, but always without the phantom (if used). In this
International Standard it is always termed a dosemeter.
Note 2 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 ionisation 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 3 to entry: To distinguish between the indication of the standard and the dosemeter, subscripts ‘s’ and ‘d’ are used
and the respective indications are named G and G .
s d
[SOURCE: ISO/IEC Guide 99:2007, 4.1.]
3.1.16
influence quantity
quantity that, in a direct measurement, does not affect the quantity that is actually measured, but affects the
relation between the indication and the measurement result
Note 1 to entry: The correction of the effect of the influence quantity can require a correction factor (influence quantity
of type F) and/or a correction summand (influence quantity of type S) to be applied to the indication of the dosemeter, e.g.
energy for type F and microphony or electromagnetic disturbance for type S, see 3.1.9 and 3.1.12.
Note 2 to entry: The dose rate is an influence quantity when measuring the dose.
[SOURCE: ISO/IEC Guide 99:2007, 2.52.]
4 © ISO 2012 – All rights reserved

ISO 29661:2012(E)
3.1.17
instrument constant
c
i
constant by which the indication of the dosemeter, G, or — if corrections or a normalization were applied — the
corrected indication, G , is multiplied to convert it to the same unit as the measurand
corr
Note to entry: If the instrument’s indication is already expressed in the same unit as the measurand, c is unnecessary.
i
[SOURCE: ICRU Report 76.]
3.1.18
measurand
quantity intended to be measured
[SOURCE: ISO/IEC Guide 99:2007, 2.3.]
3.1.19
measured quantity value
measured value
M
quantity value representing a measurement result
Note to entry: See 6.2.4.
[SOURCE: ISO/IEC Guide 99:2007, 2.10.]
3.1.20
monitor device
device installed in an irradiation facility to monitor the fluence or dose (rate) of the irradiation field
3.1.21
personal dosemeter
meter designed to measure the personal dose equivalent (rate)
Note to entry: A personal dosemeter can be worn on the trunk (whole-body personal dosemeter), at the extremities
(extremity personal dosemeter) or close to the eye lens (eye lens dosemeter).
[SOURCE: IEV 394-22-08, modified.]
3.1.22
phantom
artefact constructed to simulate the scattering properties of the human body or parts of the human body such
as the extremities
Note to entry: A phantom can be used for the definition of a quantity and made of artificial material, e.g. ICRU tissue,
or for the calibration and then be made of physically existing material, see 6.6.2 for details.
3.1.23
point of test
point in the radiation field at which the conventional quantity value is known
[SOURCE: ICRU Report 76.]
3.1.24
primary measurement standard
primary standard
measurement standard established using a primary reference measurement procedure, or created as an
artefact, chosen by convention
EXAMPLE Free-air chambers as primary measurement standards of the measurand air kerma free-in-air.
Note 1 to entry: A primary standard has the highest metrological quality in a given field of metrology.
ISO 29661:2012(E)
Note 2 to entry: The quantity value of the primary standard is equated to the best estimate of the quantity to be measured,
i.e. the conventional quantity value.
[SOURCE: ISO/IEC Guide 99:2007, 5.4.]
3.1.25
quantity
property of a phenomenon, body or substance, where the property has a magnitude that can be expressed as
a number and a reference
[SOURCE: ISO/IEC Guide 99:2007, 1.1.]
Note to entry: The quantities considered in the scope of this International Standard are the operational quantities for
radiation protection purposes (ambient dose equivalent, directional dose equivalent, personal dose equivalent and the
respective dose rates) and the basic quantities such as air kerma free-in-air, fluence and absorbed dose to soft tissue.
3.1.26
quantity value
number and reference together expressing magnitude of a quantity
−1
EXAMPLE 1,52 µGy h as the dose rate in a given radiation field.
Note to entry: A quantity value is a product of a number and a measurement unit (the unit one is generally not indicated
for quantities of dimension one).
[SOURCE: ISO/IEC Guide 99:2007, 1.19.]
3.1.27
radiation detector
apparatus or substance used to convert incident ionizing radiation energy into a signal suitable for indication
and/or measurement
[SOURCE: IEV 394-24-01.]
3.1.28
radiation quality
U
characteristic of ionizing radiation determined by the spectral distribution of radiation with respect to energy
Note to entry: The characteristic is expressed by parameters which are given together with their values in ISO 4037,
ISO 6980, ISO 8529 and ISO 12789. Examples of the parameters are effective energy, half-value layer, X-ray tube voltage
and filtration.
[SOURCE: IEV 881-02-22, modified.]
3.1.29
reference direction
direction, in the coordinate system of the dosemeter, with respect to which the angle of radiation incidence is
measured in reference fields
Note 1 to entry: At the angle of incidence of 0° the reference direction of the dosemeter is parallel to the direction of radiation
incidence. At the angle of 180° the reference direction of the dosemeter is anti-parallel to the direction of radiation incidence.
Note 2 to entry: The reference direction, in the coordinate system of the dosemeter, points into the dosemeter (see
Figure 1). For parts to be irradiated consisting of a personal dosemeter and a cylindrical phantom such as a pillar or rod
phantom the reference direction points into the phantom and is perpendicular to the centre line of the phantom.
3.1.30
reference operating condition
reference condition
operating condition prescribed for evaluating the performance of a measuring instrument or measuring system
or for comparison of measurement results
[SOURCE: ISO/IEC Guide 99:2007, 4.11.]
6 © ISO 2012 – All rights reserved

ISO 29661:2012(E)
3.1.31
reference orientation
orientation of the dosemeter for which the direction of the incident radiation coincides with the reference
direction of the dosemeter
[SOURCE: ICRU Report 76.]
3.1.32
reference point
point of the dosemeter that is placed at the point of test for calibration and test purposes
Note 1 to entry: The distance of the measurement is given by the distance between the emission point of the radiation
source and the reference point of the dosemeter.
Note 2 to entry: In the case of the calibration of a personal dosemeter, the phantom has to be included in the calibration
process, see Figure 1 and 6.6.3.
[SOURCE: ICRU Report 76, modified.]
3.1.33
reference radiation field
radiation field whose radiation quality and dosimetric parameters have values according to International
Standards or which is provided by the BIPM
Note 1 to entry: Examples of such International Standards are ISO 4037, ISO 6980, ISO 8529 and ISO 12789.
Note 2 to entry: In the upper part of Figure 1, the direction of the radiation incidence and the reference direction are
parallel, i.e. the angle of incidence is α = 0°. In the lower part of Figure 1, the direction of radiation incidence and the
reference direction have an angle of incidence of α = 45°.
3.1.34
response
R
quotient of the indication, G, or of the corrected indication, G , and the conventional quantity value to be measured
corr
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 corrected indication with respect to fluence,
R , the response of the non-corrected indication with respect to kerma, R , and the response of the corrected indication
Φ K
with respect to the absorbed dose, R .
D
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 or dose
rate). 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 RE(,Ω) of the mean radiation

energy E of the radiation quality U and the direction Ω of the incident monodirectional radiation. RE() 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.
Note 5 to entry: For the determination of the energy dependence the most accurate information is obtained experimentally
if small spectra are used, e.g. for X-rays the radiation qualities of the N series as described in ISO 4037-1.
ISO 29661:2012(E)
Key
1 personal dosemeter
2 water slab phantom
3 reference point
a
Direction of radiation incidence.
b
Reference direction.
c
Radiation incidence.
Figure 1 — Reference direction and direction of radiation incidence of personal dosemeter mounted
on water slab phantom [see 6.6.2 a)]
3.1.35
secondary measurement standard
secondary standard
measurement standard established through calibration with respect to a primary measurement standard for a
quantity of the same kind
Note 1 to entry: Calibration may be obtained directly between a primary measurement standard and a secondary
measurement standard, or involve an intermediate measuring system calibrated by the primary measurement standard
and assigning a measurement result to the secondary measurement standard.
Note 2 to entry: A secondary standard can be represented variously, e.g. as a measuring device or a radionuclide source unit.
8 © ISO 2012 – All rights reserved

ISO 29661:2012(E)
Note 3 to entry: The calibration of the secondary standard is only valid for the irradiation conditions used, e.g. energy,
dose and/or dose rate, environmental conditions.
Note 4 to entry: The quantity value of the secondary standard is equated to the best estimate of the quantity to be
measured, i.e. the conventional quantity value.
[SOURCE: ISO/IEC Guide 99:2007, 5.5.]
3.1.36
standard test conditions
conditions represented by the range of values for the influence quantities under which a calibration or
determination of the response is carried out
Note 1 to entry: Appropriate corrections to reference conditions should be made.
Note 2 to entry: Ideally, calibrations should be carried out under reference conditions. As this is not always achievable
(e.g. for ambient air pressure) or convenient (e.g. for ambient temperature) a (small) interval around the reference values
is acceptable. Values for the standard test conditions together with the reference conditions are given in Table A.1.
[SOURCE: ICRU Report 76 modified.]
3.1.37
true quantity value
quantity value consistent with the definition of a quantity
Note to entry: In the error approach to describing measurement, a true quantity value is considered unique and, in
practice, unknowable. The uncertainty approach is to recognize that, owing to the inherently incomplete amount of detail in
the definition of a quantity, there is not a single true quantity value but rather a set of true quantity values consistent with the
definition. However, this set of values is, in principle and in practice, unknowable. Other approaches dispense altogether
with the concept of true quantity value and rely on the concept of metrological compatibility of measurement results for
assessing their validity.
[SOURCE: ISO/IEC Guide 99:2007, 2.11.]
3.1.38
working measurement standard
measurement standard that is used routinely to calibrate or verify measuring instruments or measuring systems
Note to entry: According to ISO/IEC Guide 99:2007, a working measurement standard is always traceable to a
primary standard.
[SOURCE: ISO/IEC Guide 99:2007, 5.7.]
3.2 Quantities and conversion coefficients
3.2.1
absorbed dose
D
quotient of dE by dm, where dE is the mean energy imparted to matter of mass dm, thus
dE
D =
dm
−1
Note 1 to entry: The SI unit of the absorbed dose is joules per kilogram (J·kg ), known as grays (Gy).
Note 2 to entry: The full specification of the absorbed dose includes the specification of the material, e.g. soft tissue or air.

Note 3 to entry: The absorbed dose rate D is the quotient of dD by dt, where dD is the increment of the absorbed dose
−1
in time interval dt. The unit is grays per second (Gy·s ). Other units are any quotient of the gray or its decimal multiples
−1
and a suitable unit of time (e.g. mGy·h ).
[SOURCE: ICRU Report 60.]
ISO 29661:2012(E)
3.2.2
absorbed-dose-to-dose-equivalent conversion coefficient
h
D
quotient of the dose equivalent, H, and the absorbed dose, D
H
h =
D
D
−1
Note 1 to entry: The unit of the absorbed-dose-to-dose-equivalent conversion coefficient is sieverts per gray (Sv·Gy ).
Note 2 to entry: The full specification of the absorbed-dose-to-dose-equivalent conversion coefficient includes the
specification of the radiation to which it refers and of the type of dose equivalent (ambient, directional or personal), as well
as for the absorbed dose the material, e.g. air or soft tissue. The absorbed-dose-to-dose-equivalent conversion coefficient
 
h depends on the energy and, for H (10), H (3), H (0,07), H'(3;)Ω and H'(0,07;Ω) , also on the directional distribution of
D p p p
the incident radiation. Therefore, it is useful to consider the conversion coefficient as a function, h (E, α), of the energy, E,
D
of monoenergetic particles at several angles of incidence α.
 
Note 3 to entry: The conversion coefficients from D to H'(0,07;Ω) , to H'(3;)Ω , to H*(10), to H (10), to H (3) or to
p p
' '
*
H (0,07) for the radiation quality U and the angle of incidence α, are indicated as h (0,07;U,α) , h (3;U,)α , h ()10;U ,
p
D D D
h (10;U, α), h (3;U, α), and h (0,07;U, α), respectively.
pD pD pD
3.2.3
total air kerma free-in-air
K
a
quotient of dE by dm, where dE is the sum of the initial kinetic energies of all the charged particles liberated
tr tr
by uncharged particles in a mass, dm, of air at a point of interest in air
dE
tr
K =
a
dm
−1
Note 1 to entry: The SI unit of air kerma is joules per kilogram (J·kg ), known as grays (Gy).

Note 2 to entry: The air kerma rate, K ,is a quotient of dK by dt, where dK the increment of the air kerma in time
a a
a
−1
interval dt. The unit is grays per second (Gy·s ). Other units are any quotient of the gray or its decimal multiples and a
−1
suitable unit of time (e.g. mGy·h ).
Note 3 to entry: The definition given specifies the total air kerma. It is given by the sum of the collision air kerma, K ,
a,coll
and the radiative air kerma, K : K = K + K . The collision air kerma is the part of the air kerma that leads to the
a,rad a a,coll a,rad
production of electrons through Compton scattering, photoelectric effect and pair production that dissipate their energy
as ionization in or near the electron tracks in the medium. The radiative air kerma is the part of the air kerma that leads
to the production of third-generation photons as the secondary charged particles are decelerated in the medium. The
third-generation photons are produced via a) bremsstrahlung emission, b) positron annihilation in flight, c) fluorescence
emission as a result of electron- and positron-impact ionization, and d) the effects on these processes of energy-loss
straggling and knock-on electron production. This scheme goes beyond that of ICRU 33, which formally includes only a).
See Reference [37] for details.
[SOURCE: ICRU 60, modified.]
3.2.4
air kerma-to-dose-equivalent conversion coefficient
h
K
quotient of the dose equivalent, H, and the collision air kerma free-in-air, K , at a point in the photon
a,coll
radiation field
H
h =
K
K
a, coll
−1
Note 1 to entry: The unit of the air kerma-to-dose-equivalent conversion coefficient is sieverts per gray (Sv·Gy ).
Note 2 to entry: The collision air kerma is the part of the air kerma that leads to the production of electrons that dissipate
their energy as ionization in or near the electron tracks in the medium. Therefore, this collision air kerma was always meant
in the definition of the conversion coefficient, although not precisely specified. See Reference [37] for details.
10 © ISO 2012 – All rights reserved

ISO 29661:2012(E)
Note 3 to entry: The collision air kerma, K , is related to the total air kerma by the factor g : K = K · (1-g).
a,coll a,coll a
Factor g is the fraction of the energy of the secondary electrons liberated by photons that is lost by radiative processes
(bremsstrahlung, fluorescence radiation or annihilation radiation of positrons). For water or air and for energies lower than
1,3 MeV, g is less than 0,003.
Note 4 to entry: The full specification of an air kerma-to-dose-equivalent conversion coefficient includes the specification
of the type of dose equivalent, e.g. ambient, directional or personal. The conversion coefficient, h , depends on the energy
K
 
and, for H (10), H (3), H (0,07), H'(3;)Ω and H'(0,07;Ω) , also on the directional distribution of the incident radiation. It
p p p
is, therefore, useful to consider the conversion coefficient as a function, h (E, α), of the energy, E, of monoenergetic
K
photons at several angles of incidence α.
Note 5 to entry: The conversion coefficients from the air kerma free-in-air, K , to H'(0,07) , to H'(3) , to H*(10), to H (10),
a p
' '
to H (3) or to H (0,07) for the radiation quality U and the angle of incidence α are indicated as h (0,07;U,α) , h (3;U,)α ,
p p
K K
*
h ()10;U , h (10;U, α), h (3;U, α), and h (0,07;U, α), respectively.
pK pK pK
K
3.2.5
ambient dose equivalent
H*(d)
dose equivalent at a point in a radiation field that would be produced by the corresponding expanded and
aligned field, in the ICRU sphere at a depth, d, on the radius opposing the direction of the aligned field
Note 1 to entry: The SI unit of the ambient dose equivalent is joules per kilogram (J·kg-1), known as sieverts (Sv).
Note 2 to entry: In the expanded and aligned field, the fluence and its energy distribution have the same values throughout
the volume of interest as in the actual field at the point of test; the field is unidirectional.
Note 3 to entry: The full specification of the ambient dose equivalent includes the specification of the reference depth, d,
expressed in millimetres.

Note 4 to entry: The ambient dose equivalent rate, H* ()d , is the quotient of dH*(d) by dt, where dH*(d) is the increment
−1
of the ambient dose equivalent at a depth, d, in time interval dt. The unit is sieverts per second (Sv·s ). Other units are any
−1
quotient of the sievert or its decimal multiples and a suitable unit of time (e.g. mSv·h ).
[SOURCE: ICRU Report 51, modified.]
3.2.6
directional dose equivalent

H′(,007,)Ω
dose equivalent at a point in a radiation field that would be produced by the corresponding expanded field, in

the ICRU sphere at a depth, d, on a radius in a specified direction, Ω
Note 1 to entry: The SI unit of the directional dose equivalent is joules per kilogram (J·kg-1), known as sieverts (Sv).
Note 2 to entry: In a unidirectional field, the direction can be specified in terms of the angle, α, between the radius
opposing the incident field and a specified radius. For α = 0°, the quantity H′(d; 0°) may be written as H′(d).
Note 3 to entry: In the expanded field, the fluence and its angular and energy distributions have the same values
throughout the volume of interest as in the actual field at the point of test.
Note 4 to entry: The full specification of the directional dose equivalent includes the specification of the reference depth,
d, expressed in millimetres.

Note 5 to entry: The directional dose equivalent rate, H'()d , is the quotient of dH′(d) by dt, where dH′(d) is the increment
−1
of the directional dose equivalent at a depth, d, in time interval dt. The unit is sieverts per second (Sv·s ). Other units are
−1
any quotient of the sievert or its decimal multiples and a suitable unit of time (e.g. mSv·h ).
[SOURCE: ICRU Report 51, modified.]
ISO 29661:2012(E)
3.2.7
dose equivalent
H
product of Q and D at a point in tissue, w
...