IEC 62387:2012

IEC 62387 ®
Edition 1.0 2012-12
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
colour
inside
Radiation protection instrumentation – Passive integrating dosimetry systems
for personal and environmental monitoring of photon and beta radiation

Instrumentation pour la radioprotection – Systèmes dosimétriques intégrés
passifs pour la surveillance de l’individu et de l'environnement des
rayonnements photoniques et bêta

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IEC 62387 ®
Edition 1.0 2012-12
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
colour
inside
Radiation protection instrumentation – Passive integrating dosimetry systems

for personal and environmental monitoring of photon and beta radiation

Instrumentation pour la radioprotection – Systèmes dosimétriques intégrés

passifs pour la surveillance de l’individu et de l'environnement des

rayonnements photoniques et bêta

INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
COMMISSION
ELECTROTECHNIQUE
PRICE CODE
INTERNATIONALE
CODE PRIX XC
ICS 13.280 ISBN 978-2-83220-518-1

– 2 – 62387 © IEC:2012
CONTENTS
FOREWORD . 7

INTRODUCTION . 9

1 Scope . 10

2 Normative references . 11

3 Terms and definitions . 12

4 Units and symbols . 20

5 General test procedures . 21
5.1 Basic test procedures . 21
5.1.1 Instructions for use . 21
5.1.2 Nature of tests . 21
5.1.3 Reference conditions and standard test conditions . 21
5.1.4 Production of reference radiation . 21
5.1.5 Choice of phantom for the purpose of testing . 21
5.1.6 Position of dosemeter for the purpose of testing . 21
5.2 Test procedures to be considered for every test . 21
5.2.1 Number of dosemeters used for each test . 21
5.2.2 Consideration of the uncertainty of the conventional true value . 21
5.2.3 Consideration of non-linearity . 22
5.2.4 Consideration of natural background radiation . 22
5.2.5 Consideration of several detectors or signals in a dosemeter . 22
5.2.6 Performing the tests efficiently . 22
6 Performance requirements: summary . 22
7 Capability of a dosimetry system . 23
7.1 General . 23
7.2 Measuring range and type of radiation . 23
7.3 Rated ranges of the influence quantities . 24
7.4 Maximum rated measurement time t . 24
max
7.5 Reusability . 24
7.6 Model function . 24
7.7 Example for the capabilities of a dosimetry system . 24
8 Requirements for the design of the dosimetry system . 25

8.1 General . 25
8.2 Indication of the dose value (dosimetry system) . 25
8.3 Assignment of the dose value to the dosemeter (dosimetry system) . 25
8.4 Information given on the devices (reader and dosemeter) . 25
8.5 Retention and removal of radioactive contamination (dosemeter) . 26
8.6 Algorithm to evaluate the indicated value (dosimetry system) . 26
8.7 Use of dosemeters in mixed radiation fields (dosimetry system) . 26
9 Instruction manual . 26
9.1 General . 26
9.2 Specification of the technical data . 27
10 Software, data and interfaces of the dosimetry system . 28
10.1 General . 28
10.2 Design and structure of the software . 28
10.2.1 Requirements . 28

62387 © IEC:2012 – 3 –
10.2.2 Method of test . 28

10.3 Identification of the software . 28

10.3.1 Requirements . 28

10.3.2 Method of test . 29

10.4 Authenticity of the software and the presentation of results . 29

10.4.1 Requirements . 29

10.4.2 Method of test . 29

10.5 Alarm and stop of system operation under abnormal operating conditions . 29

10.5.1 Requirements . 29

10.5.2 Method of test . 30

10.6 Control of input data by the dosimetry system . 30
10.6.1 Requirements . 30
10.6.2 Method of test . 30
10.7 Storage of data . 30
10.7.1 Requirements . 30
10.7.2 Method of test . 31
10.8 Transmission of data . 31
10.8.1 Requirements . 31
10.8.2 Method of test . 32
10.9 Hardware interfaces and software interfaces . 32
10.9.1 Requirements . 32
10.9.2 Method of test . 32
10.10 Documentation for the software test . 33
10.10.1 Requirements . 33
10.10.2 Method of test . 33
11 Radiation performance requirements and tests (dosimetry system). 33
11.1 General . 33
11.2 Coefficient of variation. 34
11.3 Non-linearity . 34
11.3.1 Requirements . 34
11.3.2 Method of test . 34
11.3.3 Interpretation of results. 34
11.4 Overload characteristics, after-effects, and reusability . 36
11.4.1 Requirements . 36
11.4.2 Method of test . 36

11.4.3 Interpretation of the results . 36
11.5 Radiation energy and angle of incidence for H (10) or H*(10) dosemeters . 37
p
11.5.1 Photon radiation . 37
11.5.2 Beta radiation . 38
11.6 Radiation energy and angle of incidence for H (3) dosemeters . 39
p
11.6.1 Photon radiation . 39
11.6.2 Beta radiation . 40
11.7 Radiation energy and angle of incidence for H (0,07) or H ’(0,07) dosemeters . 41
p
11.7.1 Photon radiation . 41
11.7.2 Beta radiation . 42
11.8 Over response to radiation incidence from the side of an H (10), H (3) or
p p
H (0,07) dosemeter. 43
p
11.8.1 Requirements . 43
11.8.2 Method of test . 44

– 4 – 62387 © IEC:2012
11.8.3 Interpretation of the results . 44

11.9 Indication of the presence of beta dose for H (0,07) whole body dosemeters . 44
p
12 Response to mixed irradiations (dosimetry system) . 44

12.1 Requirements . 44

12.2 Method of test . 45

12.2.1 General . 45

12.2.2 Preparation of the test . 45

12.2.3 Practical test . 45

12.3 Interpretation of the results . 46

13 Environmental performance requirements and tests . 46
13.1 General . 46
13.1.1 General requirement . 46
13.1.2 General method of test . 46
13.2 Ambient temperature and relative humidity (dosemeter) . 47
13.2.1 General . 47
13.2.2 Requirements . 47
13.2.3 Method of test . 47
13.2.4 Interpretation of the results . 47
13.3 Light exposure (dosemeter) . 48
13.3.1 General . 48
13.3.2 Requirements . 48
13.3.3 Method of test . 48
13.3.4 Interpretation of the results . 48
13.4 Dose build-up, fading, self-irradiation, and response to natural radiation
(dosemeter) . 48
13.4.1 General . 48
13.4.2 Requirements . 49
13.4.3 Method of test . 49
13.4.4 Interpretation of the results . 49
13.5 Sealing (dosemeter) . 50
13.6 Reader stability (reader) . 50
13.6.1 General . 50
13.6.2 Requirements . 50
13.6.3 Method of test . 50
13.6.4 Interpretation of the results . 50

13.7 Ambient temperature (reader). 51
13.7.1 General . 51
13.7.2 Requirements . 51
13.7.3 Method of test . 51
13.7.4 Interpretation of the results . 51
13.8 Light exposure (reader) . 51
13.8.1 General . 51
13.8.2 Requirements . 52
13.8.3 Method of test . 52
13.8.4 Interpretation of the results . 52
13.9 Primary power supply (reader). 52
13.9.1 General . 52
13.9.2 Requirements . 52
13.9.3 Method of test . 53

62387 © IEC:2012 – 5 –
13.9.4 Interpretation of the results . 53

14 Electromagnetic performance requirements and tests (dosimetry system) . 53

14.1 General . 53

14.2 Requirement . 53

14.3 Method of test . 54

14.4 Interpretation of the results . 54

15 Mechanical performance requirements and tests . 54

15.1 General requirement . 54

15.2 Drop (dosemeter) . 55

15.2.1 Requirements . 55
15.2.2 Method of test . 55
15.2.3 Interpretation of the results . 55
16 Documentation . 55
16.1 Type test report . 55
16.2 Certificate issued by the laboratory performing the type test . 56
Annex A (normative) Confidence limits. 68
Annex B (informative) Causal connection between readout signals, indicated value
and measured value . 71
Annex C (informative) Overview of the necessary actions that have to be performed
for a type test according to this standard . 72
Annex D (informative) Usage categories of passive dosemeters . 74
Annex E (informative) Uncertainty of dosimetry systems . 75
Annex F (informative) Conversion coefficients h (3;α), h (0,07;α), and h ’ (0,07;α)
pK pK K
from air kerma, K , to the dose equivalent H (3), H (0,07), and H ’(0,07), respectively,
a p p
for radiation qualities defined in ISO 4037-1 . 76
Annex G (informative) Conversion coefficients h (0,07;source;α) and h (3;source;α)
pD pD
from personal absorbed dose in 0,07 mm depth, D (0,07), to the dose equivalent
p
H (0,07) and H (3), respectively, for radiation qualities defined in ISO 6980-1 . 78
p p
Annex H (informative) Computational method of test for mixed irradiations . 79
Bibliography . 81

Figure A.1 – Test for confidence interval . 68
Figure B.1 – Data evaluation in dosimetry systems . 71
Figure H.1 – Flow chart of a computer program to perform tests according to 12.2 . 80

Table 1 – Mandatory and maximum energy ranges covered by this standard . 10
Table 2 – Values of c and c for w different dose values and n indications for each
1 2
dose value . 35
Table 3 – Angular irradiations for H (10) and H*(10) dosemeters . 37
p
Table 4 – Angular irradiations for H (3) dosemeters . 39
p
Table 5 – Angular irradiations for H (0,07) and H ’(0,07) dosemeters . 41
p
Table 6 – Symbols . 57
Table 7 – Reference conditions and standard test conditions . 59
Table 8 – Performance requirements for H (10) dosemeters . 60
p
Table 9 – Performance requirements for H (3) dosemeters . 61
p
Table 10 – Performance requirements for H (0,07) dosemeters . 62
p
Table 11 – Performance requirements for H*(10) dosemeters . 63

– 6 – 62387 © IEC:2012
Table 12 – Performance requirements for H ’(0,07) dosemeters . 64

Table 13 – Environmental performance requirements for dosemeters and readers . 65

Table 14 – Electromagnetic disturbance performance requirements for dosimetry

systems according to Clause 14. 66

Table 15 – Mechanical disturbances performance requirements for dosemeters . 67

Table A.1 – Student’s t-value for a double sided 95 % confidence interval . 69

Table C.1 – Schedule for a type test of a dosemeter for H (10) fulfilling the
p
requirements within the mandatory ranges . 72

Table D.1 – Usage categories of passive dosemeters . 74

Table F.1 – Conversion coefficients h (3;N,α) from air kerma, K , to the dose
pK a
equivalent H (3) for radiation qualities defined in ISO 4037-1 and for the slab
p
phantom, reference distance 2 m . 76
Table F.2 – Conversion coefficients h (3;S,α) and h (3;R,α) from air kerma, K , to
pK pK a
the dose equivalent H (3) for radiation qualities defined in ISO 4037-1 and for the
p
slab phantom . 77
Table F.3 – Conversion coefficients h (0,07;S,α) and h (0,07;R,α) from air kerma,
pK pK
K , to the dose equivalent H (0,07) for radiation qualities defined in ISO 4037-1 and
a p
for the rod, pillar, and slab phantom . 77
Table F.4 – Conversion coefficients h ’ (0,07;N,α), h ’ (0,07;S,α), and h ’ (0,07;R,α)
K K K
from air kerma, K , to H ’(0,07) for radiation qualities defined in ISO 4037-1 . 77
a
Table G.1 – Measured conversion coefficients h (3;source;α) from personal absorbed
pD
dose in 0,07 mm depth, D (0,07), to the dose equivalent H (3) for the slab phantom
p p
for radiation qualities defined in ISO 6980-1 . 78
Table G.2 – Measured conversion coefficients h (0,07;source;α) from personal
pD
absorbed dose in 0,07 mm depth, D (0,07), to the dose equivalent H (0,07) for the
p p
slab phantom for radiation qualities defined in ISO 6980-1 . 78

62387 © IEC:2012 – 7 –
INTERNATIONAL ELECTROTECHNICAL COMMISSION

____________
RADIATION PROTECTION INSTRUMENTATION –

PASSIVE INTEGRATING DOSIMETRY SYSTEMS FOR PERSONAL

AND ENVIRONMENTAL MONITORING OF PHOTON AND BETA RADIATION

FOREWORD
1) The International Electrotechnical Commission (IEC) is a worldwide organization for standardization comprising
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8) Attention is drawn to the Normative references cited in this publication. Use of the referenced publications is
indispensable for the correct application of this publication.
9) Attention is drawn to the possibility that some of the elements of this IEC Publication may be the subject of
patent rights. IEC shall not be held responsible for identifying any or all such patent rights.
International Standard IEC 62387 has been prepared by subcommittee 45B: Radiation

protection instrumentation, of IEC technical committee 45: Nuclear instrumentation.
This standard cancels and replaces IEC 62387-1 published in 2007. This edition constitutes a
technical revision.
This edition includes the following significant technical changes with respect to the previous
edition:
• Extension of the photon energy range for dosemeters to measure H (0,07) from the old
p
range of 8 keV to 250 keV to the new range of 8 keV to 10 MeV.
• Addition of performance requirements for dosemeters to measure H (3) for both photon
p
and beta radiation. Such dosemeters can be used to monitor the eye lens dose.
• Addition of performance requirements for dosemeters to measure H’(0,07) for both photon
and beta radiation.
• Correction and clarification of several subsections to obtain a better applicability.

– 8 – 62387 © IEC:2012
• Alignment of IEC performance requirements on dosimetry systems for measuring personal

dose equivalents with the recommendations on accuracy stated in ICRP Publication 75,

General Principles for the Radiation Protection of Workers. Further information is given in

the new informative Annex E.
With these changes it also covers the scope of ISO 12794:2000, Nuclear energy – Radiation
protection – Individual thermoluminescence dosemeters for extremities and eyes.

The text of this standard is based on the following documents:

FDIS Report on voting
45B/743/FDIS 45B/752/RVD
Full information on the voting for the approval of this standard can be found in the report on
voting indicated in the above table.
This publication has been drafted in accordance with the ISO/IEC Directives, Part 2.
The committee has decided that the contents of this publication will remain unchanged until
the stability date indicated on the IEC web site under "http://webstore.iec.ch" in the data
related to the specific publication. At this date, the publication will be
• reconfirmed,
• withdrawn,
• replaced by a revised edition, or
• amended.
IMPORTANT – The 'colour inside' logo on the cover page of this publication indicates
that it contains colours which are considered to be useful for the correct
understanding of its contents. Users should therefore print this document using a
colour printer.
62387 © IEC:2012 – 9 –
INTRODUCTION
A dosimetry system may consist of the following elements:

a) a passive device, referred to here as a detector, which, after the exposure to radiation,

stores a signal for use in measuring one or more quantities of the incident radiation field;

b) a “dosemeter”, that incorporates some means of identification and contains one or more

detectors and may contain electronic components;

c) a “reader” which is used to readout the stored information (signal) from the detector, in
order to determine the radiation dose;

d) a “computer” with appropriate “software” to control the reader, store the signals
transmitted from the reader, calculate, display and store the evaluated dose in the form of
an electronic file or paper copy;
e) “additional equipment” and documented procedures (instruction manual) for performing
associated processes such as deleting stored dose information, cleaning dosemeters, or
those needed to ensure the effectiveness of the whole system.

– 10 – 62387 © IEC:2012
RADIATION PROTECTION INSTRUMENTATION –

PASSIVE INTEGRATING DOSIMETRY SYSTEMS FOR PERSONAL

AND ENVIRONMENTAL MONITORING OF PHOTON AND BETA RADIATION

1 Scope
This standard applies to all kinds of passive dosimetry systems that are used for measuring

– the personal dose equivalent H (10) (for whole body dosimetry),
p
– the personal dose equivalent H (3) (for eye lens dosimetry),
p
– the personal dose equivalent H (0,07) (for both whole body and extremity dosimetry),
p
– the ambient dose equivalent H*(10) (for environmental dosimetry), or
– the directional dose equivalent H ’(0,07) (for environmental dosimetry).
NOTE 1 The term “environmental dosimetry” means ambient, area, and environmental monitoring in this standard.
This standard applies to dosimetry systems that measure external photon and/or beta
radiation in the dose range between 0,01 mSv and 10 Sv and in the energy ranges given in
Table 1. All the energy values are mean energies with respect to the prevailing dose quantity.
The dosimetry systems usually use electronic devices for the data evaluation and thus are
often computer controlled.
Table 1 – Mandatory and maximum energy ranges covered by this standard
Measuring Mandatory energy Maximum energy Mandatory energy Maximum energy range for
quantity range for photon range for testing range for beta- testing beta-particle

a a
radiation photon radiation particle radiation radiation
H (10),
p
80 keV to 1,25 MeV 12 keV to 10 MeV – –
H*(10)
0,8 MeV
b
0,7 MeV to 1,2 MeV
almost equivalent
H (3) 30 keV to 250 keV 8 keV to 10 MeV almost equivalent to E
p max
to an E of
max
from 2,27 MeV to 3,54 MeV
2,27 MeV
c
0,8 MeV 0,06 MeV to 1,2 MeV
H (0,07), almost equivalent almost equivalent to E
p max
30 keV to 250 keV 8 keV to 10 MeV
H ’(0,07) to an E of from 0,225 MeV to
max
2,27 MeV 3,54 MeV
a 147
The following beta radiation source are suggested for the different mean energies: For 0,06 MeV: Pm;
90 90 106 106
for 0,8 MeV: Sr/ Y; for 1,2 Mev: Ru/ Rh.

b
For beta-particle radiation, an energy of 0,7 MeV is required to reach the radiation sensitive layers of the
eye lens in a depth of about 3 mm (approximately 3 mm of ICRU tissue).
c
For beta-particle radiation, an energy of 0,07 MeV is required to penetrate the dead layer of skin of 0,07 mm

(approximately 0,07 mm of ICRU tissue).

NOTE 2 In this standard, “dose” means dose equivalent, unless otherwise stated.
NOTE 3 For H (10) and H*(10) no beta radiation is considered. Reasons: 1) H (10) and H*(10) are a conservative
p p
estimate for the effective dose which is not a suitable quantity for beta radiation. 2) No conversion coefficients are
available in ICRU 56, ICRU 57 or ISO 6980-3.
NOTE 4 The maximum energy ranges are the energy limits within which type tests according to this standard are
possible.
The test methods concerning the design (Clause 8), the instruction manual (Clause 9), the
software (Clause 10), environmental influences (Clause 13), electromagnetic influences
(Clause 14), mechanical influences (Clause 15), and the documentation (Clause 16) are

62387 © IEC:2012 – 11 –
independent of the type of radiation. Therefore, they can also be applied to other dosimetry

systems, e.g. for neutrons, utilizing the corresponding type of radiation for testing.

This standard is intended to be applied to dosimetry systems that are capable of evaluating

doses in the required quantity and unit (Sv) from readout signals in any quantity and unit. The

only correction that may be applied to the evaluated dose (indicated value) is the one

resulting from natural background radiation using extra dosemeters.

NOTE 5 The correction due to natural background can be made before or after the dose calculation.

2 Normative references
The following documents, in whole or in part, are normatively referenced in this document and
are indispensable for its application. For dated references, only the edition cited applies. For
undated references, the latest edition of the referenced document (including any
amendments) applies.
IEC 61000-4-2, Electromagnetic compatibility (EMC) – Part 4-2: Testing and measurement
techniques – Electrostatic discharge immunity test
IEC 61000-4-3, Electromagnetic compatibility (EMC) – Part 4-3: Testing and measurement
techniques – Radiated, radio-frequency, electromagnetic field immunity test
IEC 61000-4-4, Electromagnetic compatibility (EMC) – Part 4-4: Testing and measurement
techniques – Electrical fast transient/burst immunity test
IEC 61000-4-5, Electromagnetic compatibility (EMC) – Part 4-5: Testing and measurement
techniques – Surge immunity test
IEC 61000-4-6, Electromagnetic compatibility (EMC) – Part 4-6: Testing and measurement
techniques – Immunity to conducted disturbances, induced by radio-frequency fields
IEC 61000-4-8, Electromagnetic compatibility (EMC) – Part 4-8: Testing and measurement
techniques – Power frequency magnetic field immunity test
IEC 61000-4-11, Electromagnetic compatibility (EMC) – Part 4-11: Testing and measurement
techniques – Voltage dips, short interruptions and voltage variations immunity tests
IEC 61000-6-2, Electromagnetic compatibility (EMC) – Part 6-2: Generic standards –
Immunity for industrial environments

ISO 4037 (all parts), X and gamma reference radiation for calibrating dosemeters and
doserate meters and for determining their response as a function of photon energy
ISO 4037-3:1999, X and gamma reference radiation for calibrating dosemeters and doserate
meters and for determining their response as a function of photon energy – Part 3: Calibration
of area and personal dosemeters and the measurement of their response as a function of
energy and angle of incidence
ISO 6980 (all parts), Nuclear energy – Reference beta-particle radiation
ISO 6980-3, Nuclear energy – Reference beta-particle radiation – Part 3: Calibration of area
and personal dosemeters and the determination of their response as a function of beta
radiation energy and angle of incidence
ISO 8529 (all parts), Reference neutron radiations

– 12 – 62387 © IEC:2012
ISO/IEC Guide 98-3:2008, Uncertainty of measurement – Part 3: Guide to the expression of

uncertainty in measurement (GUM:1995)

3 Terms and definitions
For the purposes of this document, the following terms and definitions apply.

NOTE The terms are listed in alphabetical order.

3.1
ambient dose equivalent
H*(d)
at a point in a radiation field, dose equivalent 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 recommended depth, d, for environmental monitoring in terms of H*(d) is
...