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 4037-3:2019)

This document specifies additional procedures and data for the calibration of dosemeters and doserate meters used for individual and area monitoring in radiation protection. The general procedure for the calibration and the determination of the response of radiation protection dose(rate)meters is described in ISO 29661 and is followed as far as possible. For this purpose, the photon reference radiation fields with mean energies between 8 keV and 9 MeV, as specified in ISO 4037-1, are used. In Annex D some additional information on reference conditions, required standard test conditions and effects associated with electron ranges are given. For individual monitoring, both whole body and extremity dosemeters are covered and for area monitoring, both portable and installed dose(rate)meters are covered.
Charged particle equilibrium is needed for the reference fields although this is not always established in the workplace fields for which the dosemeter should be calibrated. This is especially true at photon energies without inherent charged particle equilibrium at the reference depth d, which depends on the actual combination of energy and reference depth d. Electrons of energies above 65 keV, 0,75 MeV and 2,1 MeV can just penetrate 0,07 mm, 3 mm and 10 mm of ICRU tissue, respectively, and the radiation qualities with photon energies above these values are considered as radiation qualities without inherent charged particle equilibrium for the quantities defined at these depths. This document also deals with the determination of the response as a function of photon energy and angle of radiation incidence. Such measurements can represent part of a type test in the course of which the effect of further influence quantities on the response is examined.
This document is only applicable for air kerma rates above 1 µGy/h.
This document does not cover the in-situ calibration of fixed installed area dosemeters.
The procedures to be followed for the different types of dosemeters are described. Recommendations are given on the phantom to be used and on the conversion coefficients to be applied. Recommended conversion coefficients are only given for matched reference radiation fields, which are specified in ISO 4037-1:2019, Clauses 4 to 6. ISO 4037‑1:2019, Annexes A and B, both informative, include fluorescent radiations, the gamma radiation of the radionuclide 241Am, S-Am, for which detailed published information is not available. ISO 4037-1:2019, Annex C, gives additional X radiation fields, which are specified by the quality index. For all these radiation qualities, conversion coefficients are given in Annexes A to C, but only as a rough estimate as the overall uncertainty of these conversion coefficients in practical reference radiation fields is not known.
NOTE The term dosemeter is used as a generic term denoting any dose or doserate meter for individual or area monitoring.

Strahlenschutz - Röntgen- und Gamma-Referenzstrahlungsfelder zur Kalibrierung von Dosimetern und Dosisleistungsmessgeräten und zur Bestimmung ihres Ansprechvermögens als Funktion der Photonenenergie - Teil 3: Kalibrierung von Orts- und Personendosimetern und Messung ihres Ansprechvermögens als Funktion von Energie und Einfallswinkel (ISO 4037-3:2019)

Dieses Dokument legt zusätzliche Verfahren und Daten zur Kalibrierung von Dosimetern und Dosisleis-tungsmessgeräten fest, die im Strahlenschutz für die Orts- und Personendosis-Überwachung verwendet wer-den. Das allgemeine Verfahren für die Kalibrierung und die Bestimmung des Ansprechvermögens von Strahlenschutz-Dosimetern und -Dosisleistungsmessgeräten ist in ISO 29661 beschrieben, und ihm wird soweit wie möglich gefolgt. Zu diesem Zweck werden die in ISO 4037 1 festgelegten Photonen-Referenz-strahlungsfelder mit mittleren Energien zwischen 8 keV und 9 MeV verwendet. In Anhang D werden einige zusätzliche Informationen über Bezugsbedingungen, geforderte Standardprüfbedingungen und Effekte im Zusammenhang mit Elektronenreichweiten angegeben. Für die Personendosimetrie werden sowohl Ganz-körper- als auch Teilkörper-Dosimeter und für die Ortsdosimetrie sowohl tragbare als auch fest installierte Dosis(leistungs)messgeräte abgedeckt.
Im Referenzstrahlungsfeld ist Sekundärteilchengleichgewicht geladener Teilchen notwendig, obwohl dieses nicht immer im Arbeitsplatzfeld, für das das Dosimeter kalibriert werden soll, vorhanden ist. Dies gilt insbe-sondere bei Photonenenergien ohne inhärentes Sekundärteilchengleichgewicht in der Bezugstiefe d, diese Eigenschaft hängt von der aktuellen Kombination von Energie und Bezugstiefe d. ab. Elektronen mit Ener-gien oberhalb von 65 keV, 0,75 MeV und 2,1 MeV können jeweils gerade 0,07 mm, 3 mm und 10 mm von ICRU-Gewebe durchdringen, und die Strahlungsqualitäten mit Photonenenergien oberhalb dieser Werte wer-den als Strahlungsqualitäten ohne inhärentes Sekundärteilchengleichgewicht für die in diesen Tiefen defi-nierten Größen angesehen. Dieses Dokument behandelt auch die Bestimmung des Ansprechvermögens als Funktion von Photonenenergie und Strahleneinfallswinkel. Derartige Messungen können einen Teil einer Bauartprüfung darstellen, in deren Verlauf die Auswirkung weiterer Einflussgrößen auf das Ansprechvermö-gen untersucht wird.
Dieses Dokument ist nur anzuwenden für Luftkermaleistungen größer als 1 Gy/h.
Dieses Dokument deckt nicht die Vor-Ort-Kalibrierung von fest installierten Ortsdosimetern ab.
Es werden die Verfahren beschrieben, die für die verschiedenen Arten von Dosimetern anzuwenden sind. Es werden Empfehlungen angegeben, welche Phantome zu verwenden und welche Konversionskoeffizienten anzuwenden sind. Empfohlene Konversionskoeffizienten werden nur für übereinstimmende Referenzstrah-lungsfelder angegeben, die in ISO 4037 1:2019, Abschnitte 4 bis 6, festgelegt sind. ISO 4037 1:2019, Anhänge A und B, beide informativ, beinhalten Fluoreszenzstrahlungen und die Gammastrahlung des Radio-nuklids 241Am, S-Am, für die detaillierte veröffentlichte Informationen nicht verfügbar sind. ISO 4037 1:2019, Anhang C, enthält zusätzliche Röntgenstrahlungsfelder, die mittels des Qualitätsindexes festgelegt sind. Für alle diese Strahlungsqualitäten werden in den informativen Anhängen A bis C Konversionskoeffizienten angegeben, aber nur als grobe Schätzwerte, da die Gesamtmessunsicherheit dieser Konversionskoeffizien-ten in praktischen Referenzstrahlungsfeldern nicht bekannt ist.
ANMERKUNG Der Begriff Dosimeter dient als Oberbegriff für jedes Dosis- oder Dosisleistungsmessgerät für die Per¬sonen- oder Ortsdosimetrie.

Radioprotection - Rayonnements X et gamma de référence pour l'étalonnage des dosimètres et des débitmètres et pour la détermination de leur réponse en fonction de l'énergie des photons - Partie 3: Étalonnage des dosimètres de zone et individuels et mesurage de leur réponse en fonction de l'énergie et de l'angle d'incidence (ISO 4037-3:2019)

Le présent document spécifie des procédures supplémentaires et des données pour l'étalonnage des dosimètres et des débitmètres utilisés pour les surveillances individuelles et de zone en radioprotection. La procédure générale pour l'étalonnage et la détermination de la réponse des dosimètres ou des débitmètres de radioprotection est décrite dans l'ISO 29661 et suivie autant que possible. À cet effet, les champs de rayonnement de référence pour les photons d'énergies moyennes comprises entre 8 keV et 9 MeV, tels que spécifiés dans l'ISO 4037‑1, sont utilisés. L'Annexe D fournit certaines informations supplémentaires relatives aux conditions de référence, aux conditions normales d'essai requises et aux effets associés aux parcours des électrons. Pour la surveillance individuelle, les dosimètres «corps entier» et d'extrémités sont concernés, tandis que pour la surveillance de zone, les dosimètres et les débitmètres portables et à poste fixe sont considérés.
Des conditions d'équilibre électronique sont nécessaires pour les champs de référence, bien que celles-ci ne soient pas toujours établies au poste de travail pour lequel il convient que le dosimètre soit étalonné. Ceci est, en particulier, vrai à des énergies de photons sans condition d'équilibre électronique inhérente à la profondeur de référence d, qui dépend de la combinaison réelle de l'énergie et de la profondeur de référence d. Les électrons d'énergies supérieures à 65 keV, 0,75 MeV et 2,1 MeV peuvent seulement pénétrer respectivement 0,07 mm, 3 mm et 10 mm de tissu de l'ICRU, et les qualités de rayonnement avec des énergies de photons supérieures à ces valeurs sont considérées comme des qualités de rayonnement sans condition d'équilibre électronique inhérente pour les qualités définies à ces profondeurs. Le présent document traite également de la détermination de la réponse en fonction de l'énergie des photons et de l'angle d'incidence du rayonnement. De tels mesurages peuvent représenter une partie d'un essai de type au cours duquel l'effet d'autres grandeurs d'influence sur la réponse est examiné.
Le présent document est applicable uniquement pour des débits de kerma dans l'air supérieurs à 1 µGy/h.
Le présent document ne traite pas de l'étalonnage in situ de dosimètres de zone à poste fixe.
Les procédures à suivre pour les différents types de dosimètres sont décrites. Des recommandations sont données concernant le fantôme à utiliser et les coefficients de conversion à appliquer. Les coefficients de conversion recommandés sont donnés uniquement pour les champs de rayonnement de référence adaptés qui sont spécifiés dans l'ISO 4037‑1:2019, Articles 4 à 6. L'ISO 4037‑1:2019, Annexes A et B, toutes deux informatives, incluent des rayonnements de fluorescence, du rayonnement gamma du radionucléide 241Am, S-Am pour lesquels des informations détaillées, publiées ne sont pas disponibles. L'ISO 4034‑1:2019, Annexe C, donne des champs de rayonnement X supplémentaires, qui sont spécifiés par l'indice de qualité. Pour toutes ces qualités de rayonnement, des coefficients de conversion sont donnés dans les Annexes A à C, mais uniquement comme une estimation approximative puisque l'incertitude globale de ces coefficients de conversion dans les champs de rayonnement de référence pratiques n'est pas connue.
NOTE Le terme dosimètre est un terme générique désignant tout dosimètre ou débitmètre pour la surveillance individuelle ou de zone.

Radiološka zaščita - Referenčno sevanje z rentgenskimi in gama žarki za kalibracijo dozimetrov in merilnikov doze sevanja ter za ugotavljanje njihovega odzivanja kot funkcije fotonske energije - 3. del: Kalibriranje zunanjih in osebnih dozimetrov ter merjenje njihovega odzivanja kot funkcije energije in vpadnega kota (ISO 4037-3:2019)

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SLOVENSKI STANDARD
SIST EN ISO 4037-3:2021
01-april-2021
Radiološka zaščita - Referenčno sevanje z rentgenskimi in gama žarki za
kalibracijo dozimetrov in merilnikov doze sevanja ter za ugotavljanje njihovega

odzivanja kot funkcije fotonske energije - 3. del: Kalibriranje zunanjih in osebnih

dozimetrov ter merjenje njihovega odzivanja kot funkcije energije in vpadnega
kota (ISO 4037-3:2019)

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 4037-3:2019)

Strahlenschutz - Röntgen- und Gamma-Referenzstrahlungsfelder zur Kalibrierung von

Dosimetern und Dosisleistungsmessgeräten und zur Bestimmung ihres

Ansprechvermögens als Funktion der Photonenenergie - Teil 3: Kalibrierung von Orts-

und Personendosimetern und Messung ihres Ansprechvermögens als Funktion von
Energie und Einfallswinkel (ISO 4037-3:2019)
Radioprotection - Rayonnements X et gamma de référence pour l'étalonnage des

dosimètres et des débitmètres et pour la détermination de leur réponse en fonction de

l'énergie des photons - Partie 3: Étalonnage des dosimètres de zone et individuels et

mesurage de leur réponse en fonction de l'énergie et de l'angle d'incidence (ISO 4037-

3:2019)
Ta slovenski standard je istoveten z: EN ISO 4037-3:2021
ICS:
13.280 Varstvo pred sevanjem Radiation protection
17.240 Merjenje sevanja Radiation measurements
SIST EN ISO 4037-3:2021 en,fr,de

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

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SIST EN ISO 4037-3:2021
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SIST EN ISO 4037-3:2021
EN ISO 4037-3
EUROPEAN STANDARD
NORME EUROPÉENNE
February 2021
EUROPÄISCHE NORM
ICS 17.240
English Version
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 4037-3:2019)

Radioprotection - Rayonnements X et gamma de Strahlenschutz - Röntgen- und Gamma-

référence pour l'étalonnage des dosimètres et des Referenzstrahlungsfelder zur Kalibrierung von

débitmètres et pour la détermination de leur réponse Dosimetern und Dosisleistungsmessgeräten und zur

en fonction de l'énergie des photons - Partie 3: Bestimmung ihres Ansprechvermögens als Funktion

Étalonnage des dosimètres de zone et individuels et der Photonenenergie - Teil 3: Kalibrierung von Orts-

mesurage de leur réponse en fonction de l'énergie et de und Personendosimetern und Messung ihres

l'angle d'incidence (ISO 4037-3:2019) Ansprechvermögens als Funktion von Energie und

Einfallswinkel (ISO 4037-3:2019)
This European Standard was approved by CEN on 18 January 2021.

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, Turkey and

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

© 2021 CEN All rights of exploitation in any form and by any means reserved Ref. No. EN ISO 4037-3:2021 E

worldwide for CEN national Members.
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SIST EN ISO 4037-3:2021
EN ISO 4037-3:2021 (E)
Contents Page

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

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SIST EN ISO 4037-3:2021
EN ISO 4037-3:2021 (E)
European foreword

The text of ISO 4037-3:2019 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 4037-3:2021 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 August 2021, and conflicting national standards shall

be withdrawn at the latest by August 2021.

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, 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, Turkey and the

United Kingdom.
Endorsement notice

The text of ISO 4037-3:2019 has been approved by CEN as EN ISO 4037-3:2021 without any

modification.
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SIST EN ISO 4037-3:2021
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SIST EN ISO 4037-3:2021
INTERNATIONAL ISO
STANDARD 4037-3
Second edition
2019-01
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
Radioprotection — Rayonnements X et gamma de référence
pour l'étalonnage des dosimètres et des débitmètres et pour la
détermination de leur réponse en fonction de l'énergie des photons —
Partie 3: Étalonnage des dosimètres de zone et individuels et
mesurage de leur réponse en fonction de l'énergie et de l'angle
d'incidence
Reference number
ISO 4037-3:2019(E)
ISO 2019
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SIST EN ISO 4037-3:2021
ISO 4037-3:2019(E)
COPYRIGHT PROTECTED DOCUMENT
© ISO 2019

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

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below or ISO’s member body in the country of the requester.
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Email: copyright@iso.org
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Published in Switzerland
ii © ISO 2019 – All rights reserved
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SIST EN ISO 4037-3:2021
ISO 4037-3:2019(E)
Contents Page

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

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

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

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

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

4 Procedures applicable to all area and personal dosemeters ................................................................................. 2

4.1 General principles ................................................................................................................................................................................ 2

4.1.1 Radiation qualities ......................................................................................................................................................... 2

4.1.2 Recommended conversion coefficients ........................................................................................................ 3

4.1.3 Point of test and reference point ........................................................................................................................ 4

4.1.4 Axes of rotation ................................................................................................................................................................. 4

4.1.5 Condition of the dosemeter to be calibrated ........................................................................................... 5

4.1.6 Effects associated with electron ranges ....................................................................................................... 5

4.2 Methods for the determination of the calibration factor and of the response ................................. 6

4.2.1 Operation of the standard instrument .......................................................................................................... 6

4.2.2 Measurements without a monitor for the source output ............................................................. 7

5 Particular procedures for area dosemeters ............................................................................................................................. 7

5.1 General principles ................................................................................................................................................................................ 7

5.2 Quantities to be measured ............................................................................................................................................................ 7

6 Conversion coefficients for area dosimetry ............................................................................................................................. 7

6.1 Conversion coefficients from air kerma, K , to H'(0,07) ...................................................................................... 7

6.1.1 Mono-energetic radiation ........................................................................................................................................ 7

6.1.2 Low air kerma rate series......................................................................................................................................... 8

6.1.3 Narrow series ..................................................................................................................................................................... 8

6.1.4 Wide series ........................................................................................................................................................................... 8

6.1.5 High air kerma rate series........................................................................................................................................ 8

6.1.6 Radionuclides ..................................................................................................................................................................... 8

6.2 Conversion coefficients from air kerma, K , to H'(3) ..........................................................................................15

6.2.1 Mono-energetic radiation .....................................................................................................................................15

6.2.2 Low air kerma rate series......................................................................................................................................15

6.2.3 Narrow series ..................................................................................................................................................................15

6.2.4 Wide series ........................................................................................................................................................................15

6.2.5 High air kerma rate series.....................................................................................................................................15

6.2.6 Radionuclides ..................................................................................................................................................................15

6.2.7 High energy photon radiations .........................................................................................................................15

6.3 Conversion coefficient from air kerma, K , to H*(10).........................................................................................23

6.3.1 Mono-energetic radiation .....................................................................................................................................23

6.3.2 Low air kerma rate series......................................................................................................................................23

6.3.3 Narrow series ..................................................................................................................................................................23

6.3.4 Wide series ........................................................................................................................................................................23

6.3.5 High air kerma rate series.....................................................................................................................................23

6.3.6 Radionuclides ..................................................................................................................................................................23

6.3.7 High energy photon radiations .........................................................................................................................23

7 Particular procedures for personal dosemeters ..............................................................................................................27

7.1 General principles .............................................................................................................................................................................27

7.2 Quantities to be measured .........................................................................................................................................................27

7.3 Experimental conditions .............................................................................................................................................................27

7.3.1 Use of phantoms ............................................................................................................................................................27

7.3.2 Geometrical considerations in divergent beams ...............................................................................28

7.3.3 Simultaneous irradiation of several dosemeters ..............................................................................28

7.3.4 Influence of the orientation on the values of H (0,07) ................................................................29

7.3.5 Length of the rod phantom ..................................................................................................................................30

© ISO 2019 – All rights reserved iii
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SIST EN ISO 4037-3:2021
ISO 4037-3:2019(E)

8 Conversion coefficients for personal dosimetry ..............................................................................................................30

8.1 General ........................................................................................................................................................................................................30

8.2 Conversion coefficients from air kerma, K , to H (0,07) in the rod phantom ...............................30

a p

8.2.1 Mono-energetic radiations ...................................................................................................................................30

8.2.2 Low air kerma rate series......................................................................................................................................30

8.2.3 Narrow series ..................................................................................................................................................................30

8.2.4 Wide series ........................................................................................................................................................................30

8.2.5 High air kerma rate series.....................................................................................................................................30

8.2.6 Radionuclides ..................................................................................................................................................................31

8.3 Conversion coefficients from air kerma, K , to H (0,07) in the pillar phantom ..........................34

a p

8.3.1 Mono-energetic radiations ...................................................................................................................................34

8.3.2 Low air kerma rate series......................................................................................................................................34

8.3.3 Narrow series ..................................................................................................................................................................34

8.3.4 Wide series ........................................................................................................................................................................34

8.3.5 High air kerma rate series.....................................................................................................................................34

8.3.6 Radionuclides ..................................................................................................................................................................34

8.4 Conversion coefficients from air kerma, K , to H (0,07) in the ICRU slab phantom ................37

a p

8.4.1 Mono-energetic radiations ...................................................................................................................................37

8.4.2 Low air kerma rate series......................................................................................................................................37

8.4.3 Narrow series ..................................................................................................................................................................37

8.4.4 Wide series ........................................................................................................................................................................37

8.4.5 High air kerma rate series.....................................................................................................................................38

8.4.6 Radionuclides ..................................................................................................................................................................38

8.5 Conversion coefficients from air kerma, K , to H (3) in the cylinder phantom ...........................41

a p

8.5.1 Mono-energetic radiations ...................................................................................................................................41

8.5.2 Low air kerma rate series......................................................................................................................................41

8.5.3 Narrow series ..................................................................................................................................................................41

8.5.4 Wide series ........................................................................................................................................................................41

8.5.5 High air kerma rate series.....................................................................................................................................41

8.5.6 Radionuclides ..................................................................................................................................................................41

8.5.7 High energy photon radiations .........................................................................................................................41

8.6 Conversion coefficients from air kerma, K , to H (10) in the ICRU slab phantom ....................44

a p

8.6.1 Mono-energetic radiations ...................................................................................................................................44

8.6.2 Low air kerma rate series......................................................................................................................................45

8.6.3 Narrow series ..................................................................................................................................................................45

8.6.4 Wide series ........................................................................................................................................................................45

8.6.5 High air kerma rate series.....................................................................................................................................45

8.6.6 Radionuclides ..................................................................................................................................................................45

8.6.7 High energy photon radiations .........................................................................................................................45

9 Uncertainties .........................................................................................................................................................................................................53

9.1 Statement of uncertainties ........................................................................................................................................................53

Annex A (informative) Estimated conversion coefficients for fluorescence X radiation ............................54

Annex B (informative) Estimated conversion coefficients for gamma radiation emitted by

241

Am radionuclide ........................................................................................................................................................................................59

Annex C (informative) Estimated conversion coefficients for continuous filtered X radiation

based on the quality index ......................................................................................................................................................................61

Annex D (informative) Additional information ......................................................................................................................................63

Bibliography .............................................................................................................................................................................................................................67

iv © ISO 2019 – All rights reserved
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SIST EN ISO 4037-3:2021
ISO 4037-3:2019(E)
Foreword

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This document was prepared by Technical Committee ISO/TC 85, Nuclear energy, nuclear technologies

and radiological protection, Subcommittee SC 2, Radiological protection.

This second edition cancels and replaces the first edition (ISO 4037-3:1999), which has been technically

revised.
A list of all the parts in the ISO 4037 series can be found on the ISO website.
© ISO 2019 – All rights reserved v
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SIST EN ISO 4037-3:2021
ISO 4037-3:2019(E)
Introduction

The maintenance release of this document incorporates the improvements to high voltage generators

from 1996 to 2017 (e.g., the use of high frequency switching supplies providing nearly constant

potential), and the spectral measurements at irradiation facilities equipped with such generators

[1]

(e.g., the catalogue of X-ray spectra by Ankerhold ). It also incorporates all published information

with the aim to adjust the requirements for the technical parameters of the reference fields to the

targeted overall uncertainty of about 6 % to 10 % for the phantom related operational quantities of

[2]

the International Commission on Radiation Units and Measurements (ICRU) . It does not change the

general concept of the existing ISO 4037.

ISO 4037, focusing on photon reference radiation fields, is divided into four parts. ISO 4037-1 gives the

methods of production and characterization of reference radiation fields in terms of the quantities

spectral photon fluence and air kerma free-in-air. ISO 4037-2 describes the dosimetry of the reference

radiation qualities in terms of air kerma and in terms of the phantom related operational quantities of

[2]

the International Commission on Radiation Units and Measurements (ICRU) . This document describes

the methods for calibrating and determining the response of dosemeters and doserate meters in terms

[2]

of the phantom related operational quantities of the ICRU . ISO 4037-4 gives special considerations

and additional requirements for calibration of area and personal dosemeters in low energy X reference

radiation fields, which are reference fields with generating potential ≤30 kV.

The determination of the response of dosemeters and doserate meters is essentially a three-step or

two-step process. First, a basic quantity such as air kerma is measured free-in-air at the point of t

...

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