Radiation protection instrumentation - Passive integrating dosimetry systems for environmental and personal monitoring - Part 1: General characteristics and performance requirements

Applies 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.

Instrumentation pour la radioprotection - Systèmes dosimétriques intégrés passifs pour la surveillance de l'environnement et de l'individu - Partie 1: Caractéristiques générales et exigences de fonctionnement

Est destinée aux systèmes dosimétriques qui sont capables d'évaluer des doses dans la grandeur et l'unité exigées (Sv) à partir des signaux de lecture dans chaque grandeur et unité. La seule correction qui peut être appliquée à la dose évaluée (valeur indiquée) est celle qui résulte du bruit de fond dû au rayonnement naturel en utilisant des dosimètres supplémentaires.

General Information

Status
Replaced
Publication Date
29-Jul-2007
Drafting Committee
WG 14 - TC 45/SC 45B/WG 14
Current Stage
DELPUB - Deleted Publication
Start Date
04-Dec-2012
Completion Date
13-Feb-2026

Relations

Effective Date
05-Sep-2023
Effective Date
05-Sep-2023
Standard

IEC 62387-1:2007 - Radiation protection instrumentation - Passive integrating dosimetry systems for environmental and personal monitoring - Part 1: General characteristics and performance requirements Released:7/30/2007 Isbn:2831892333

English and French language
142 pages
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Frequently Asked Questions

IEC 62387-1:2007 is a standard published by the International Electrotechnical Commission (IEC). Its full title is "Radiation protection instrumentation - Passive integrating dosimetry systems for environmental and personal monitoring - Part 1: General characteristics and performance requirements". This standard covers: Applies 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.

Applies 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.

IEC 62387-1:2007 is classified under the following ICS (International Classification for Standards) categories: 13.280 - Radiation protection. The ICS classification helps identify the subject area and facilitates finding related standards.

IEC 62387-1:2007 has the following relationships with other standards: It is inter standard links to IEC 61066:2006, IEC 62387:2012. Understanding these relationships helps ensure you are using the most current and applicable version of the standard.

IEC 62387-1:2007 is available in PDF format for immediate download after purchase. The document can be added to your cart and obtained through the secure checkout process. Digital delivery ensures instant access to the complete standard document.

Standards Content (Sample)


INTERNATIONAL IEC
STANDARD
CEI
62387-1
NORME
First edition
INTERNATIONALE
Première édition
2007-07
Radiation protection instrumentation –
Passive integrating dosimetry systems for
environmental and personal monitoring –
Part 1:
General characteristics and performance
requirements
Instrumentation pour la radioprotection –
Systèmes dosimétriques intégrés passifs pour la
surveillance de l’environnement et de l’individu –
Partie 1:
Caractéristiques générales et exigences
de fonctionnement
Reference number
Numéro de référence
IEC/CEI 62387-1:2007
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INTERNATIONAL IEC
STANDARD
CEI
62387-1
NORME
First edition
INTERNATIONALE
Première édition
2007-07
Radiation protection instrumentation –
Passive integrating dosimetry systems for
environmental and personal monitoring –
Part 1:
General characteristics and performance
requirements
Instrumentation pour la radioprotection –
Systèmes dosimétriques intégrés passifs pour la
surveillance de l’environnement et de l’individu –
Partie 1:
Caractéristiques générales et exigences
de fonctionnement
PRICE CODE
XB
CODE PRIX
Commission Electrotechnique Internationale
International Electrotechnical Commission
МеждународнаяЭлектротехническаяКомиссия
For price, see current catalogue
Pour prix, voir catalogue en vigueur

– 2 – 62387-1 © IEC:2007
CONTENTS
FOREWORD.5
INTRODUCTION.7

1 Scope and object.9
2 Normative references .10
3 Terms and definitions .11
4 Units and symbols .20
5 General test procedures .20
5.1 Basic test procedures.20
5.2 Test procedures to be considered for every test .21
6 Performance requirements: summary .22
7 Capability of a dosimetry system .22
7.1 General .22
7.2 Measuring range and type of radiation.22
7.3 Rated ranges of the influence quantities.22
7.4 Maximum rated measurement time t .22
max
7.5 Reusability .23
7.6 Model function.23
7.7 Example for the capabilities of a dosimetry system.23
8 Requirements for the design of the dosimetry system .24
8.1 General .24
8.2 Indication of the dose value (dosimetry system) .24
8.3 Assignment of the dose value to the dosemeter (dosimetry system) .24
8.4 Information given on the devices (reader and dosemeter).24
8.5 Retention and removal of radioactive contamination (dosemeter) .25
8.6 Algorithm to evaluate the indicated value (dosimetry system) .25
8.7 Use of dosemeters in mixed radiation fields (dosimetry system) .25
9 Instruction manual .25
9.1 General .25
9.2 Specification of the technical data .25
10 Software, data and interfaces of the dosimetry system .27
10.1 General .27
10.2 Requirements.27
10.3 Method of test .30
11 Radiation performance requirements and tests (dosimetry system).33
11.1 General .33
11.2 Coefficient of variation.33
11.3 Non-linearity.33
11.4 Overload characteristics, after-effects and reusability.35
11.5 Radiation energy and angle of incidence for H (10) or H*(10) dosemeters .36
p
11.6 Radiation energy and angle of incidence for H (0,07) dosemeters .38
p
11.7 Radiation incidence from the side of an H (10) or H (0,07) dosemeter .40
p p
12 Additivity of the indicated value (dosimetry system).41
12.1 Requirements.41
12.2 Method of test .42

62387-1 © IEC:2007 – 3 –
12.3 Interpretation of the results .42
13 Environmental performance requirements and tests .43
13.1 General .43
13.2 Ambient temperature and relative humidity (dosemeter) .43
13.3 Light exposure (dosemeter).44
13.4 Dose build-up, fading, self-irradiation and response to natural radiation
(dosemeter).44
13.5 Sealing (dosemeter) .46
13.6 Reader stability (reader).46
13.7 Ambient temperature (reader).46
13.8 Light exposure (reader) .47
13.9 Primary power supply (reader).48
13.10 General interpretation of the results .49
14 Electromagnetic performance requirements and tests (dosimetry system) .49
14.1 General .49
14.2 Requirement.49
14.3 Method of test .49
14.4 Interpretation of the results .50
15 Mechanical performance requirements and tests .50
15.1 General requirement .50
15.2 Drop (dosemeter) .51
16 Documentation .51
16.1 Type test report.51
16.2 Certificate issued by the laboratory performing the type test.51

Annex A (normative) Confidence limits.62
Annex B (informative) Causal connection between readout signals, indicated value
and measured value .66
Annex C (informative) Overview of the necessary actions that have to be performed
for a type test according to this standard .67
Annex D (informative) Usage categories of passive dosemeters .69

Bibliography.70

Figure A.1 – Test for confidence interval.62
Figure B.1 – Data evaluation in dosimetry systems .66

Table 1 – Symbols .53
Table 2 – Reference conditions and standard test conditions .55
Table 3 – Performance requirements for H (10) dosemeters.56
p
Table 4 – Performance requirements for H (0,07) dosemeters.57
p
Table 5 – Performance requirements for H*(10) dosemeters .58
Table 6 – Environmental performance requirements for dosemeters and readers.59
Table 7 – Electromagnetic disturbance performance requirements for dosimetry

systems according to Clause 14.60
Table 8 – Mechanical disturbances performance requirements for dosemeters .61

– 4 – 62387-1 © IEC:2007
Table A.1 – Student’s t-value for a double sided 95 % confidence interval .63
Table C.1 – Schedule for a type test of a dosemeter for H (10) fulfilling the
p
requirements within the minimal rated ranges .67
Table D.1 – Usage categories of passive dosemeters .69

62387-1 © IEC:2007 – 5 –
INTERNATIONAL ELECTROTECHNICAL COMMISSION
______________
RADIATION PROTECTION INSTRUMENTATION –
PASSIVE INTEGRATING DOSIMETRY SYSTEMS FOR
ENVIRONMENTAL AND PERSONAL MONITORING –

Part 1: General characteristics and performance requirements

FOREWORD
1) The International Electrotechnical Commission (IEC) is a worldwide organization for standardization comprising
all national electrotechnical committees (IEC National Committees). The object of IEC is to promote
international co-operation on all questions concerning standardization in the electrical and electronic fields. To
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with the International Organization for Standardization (ISO) in accordance with conditions determined by
agreement between the two organizations.
2) The formal decisions or agreements of IEC on technical matters express, as nearly as possible, an international
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between any IEC Publication and the corresponding national or regional publication shall be clearly indicated in
the latter.
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equipment declared to be in conformity with an IEC Publication.
6) All users should ensure that they have the latest edition of this publication.
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Publications.
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 62387-1 has been prepared by subcommittee 45B: Radiation
protection instrumentation, of IEC technical committee 45: Nuclear instrumentation.
The text of this standard is based on the following documents:
FDIS Report on voting
45B/544/FDIS 45B/554/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.

– 6 – 62387-1 © IEC:2007
A list of all parts of the IEC 62387 series, under the general title: Radiation protection
instrumentation – Passive integrating dosimetry systems for environmental and personal
monitoring, can be found on the IEC website.
The committee has decided that the contents of this publication will remain unchanged until
the maintenance result 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.
62387-1 © IEC:2007 – 7 –
INTRODUCTION
IEC 62387 is published in separate parts according to the following structure:
Part 1: General
General characteristics and performance requirements
Part 2: Thermoluminescence dosimetry systems
Specific characteristics of, and performance requirements for, thermoluminescence
dosimetry systems
Up to now, this part is represented by the second edition of IEC 61066.
Parts 3 and following: Other dosimetry systems
The further parts (to be published later) contain specific characteristics of, and
performance requirements for, other detectors like direct ion storage, optically
stimulated luminescence etc.
A dosimetry system may consist of the following elements:
a) a passive device, referred to here as a detector, which, after the presence of radiation,
provides and 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;
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.
The main objectives of this international standard IEC 62387-1 are to:
• specify performance requirements for complete dosimetry systems including detectors,
dosemeters, readers, and additional equipment. In addition, the corresponding methods of
test to check that these requirements are met are given in detail;
• harmonize requirements for all types of passive dosimetry systems detecting external
photon and beta radiation;
• specify the use the operational quantities according to ICRU 51;
• harmonize tests using radiation with relevant ISO standards on reference radiation and
calibration: ISO 4037 for photon radiation, ISO 6980 for beta radiation and ISO 8529 for
neutron radiation. For this reason, no conversion coefficients from air kerma (or absorbed
dose or fluence) to the operational quantities are given in this standard. Those given in
the ISO-standards are applicable;
• incorporate basic terms of the concept that a result of a measurement essentially consists
of a value and an associated uncertainty, as expounded in the introductions of IEV 311
and IEC 60359 and refer the reader to an IEC technical report for complete uncertainty
analysis in radiation protection measurements and to the GUM;

– 8 – 62387-1 © IEC:2007
• align IEC uncertainty requirements on dosimetry systems for measuring personal dose
equivalents with those stated in ICRP Publication 75: General Principles for the Radiation
Protection of Workers.
62387-1 © IEC:2007 – 9 –
RADIATION PROTECTION INSTRUMENTATION –
PASSIVE INTEGRATING DOSIMETRY SYSTEMS FOR
ENVIRONMENTAL AND PERSONAL MONITORING –

Part 1: General characteristics and performance requirements

1 Scope and object
This part of IEC 62387 applies to all kinds of passive dosimetry systems that are used for
measuring the personal dose equivalents H (10) or H (0,07) or the ambient dose equivalent
p p
H*(10). It applies to dosimetry systems that measure external photon or beta radiation in the
dose range between 0,01 mSv and 10 Sv and in the energy ranges given in the following
Table. 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.
Energy range for Energy range for
Measuring quantity
photon radiation beta-particle radiation
H (10), H*(10) 12 keV to 7 MeV ---
p
a
0,07 MeV to 1,2 MeV
H (0,07) 8 keV to 250 keV almost equivalent to E
p max
from 225 keV to 3,54 MeV
a
For beta-particle radiation, an energy of 0,07 MeV is required to penetrate the
dead layer of skin of 0,07 mm (almost equivalent to 0,07 mm of ICRU tissue) nominal
depth.
NOTE 1 In this standard, “dose” means personal or ambient dose equivalent, unless otherwise stated.
NOTE 2 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.
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 The correction due to natural background may be made before or after the dose calculation.
In this standard, requirements are stated for minimal ranges of influence quantities, for
example 80 keV to 1,25 MeV for photon energy (see Tables 3 to 5). A dosimetry system shall
at least fulfil the requirements stated for these minimal ranges. However, the manufacturer
may state larger ranges for the different influence quantities, for example 60 keV to 7 MeV.
These larger ranges are called rated ranges. In such cases, the dosimetry systems must fulfil
the requirements stated for these rated ranges. Thus, dosimetry systems can be classified by
stating a set of ranges (for dose, energy, temperature etc.) within which the requirements
stated in this standard are met (Capabilities of the system, see Clause 7). In addition, usage
categories are given in Annex D with respect to different measuring capabilities.

– 10 – 62387-1 © IEC:2007
For the dosimetry systems described above, this standard specifies general characteristics,
general test procedures and performance requirements, radiation characteristics as well as
environmental, electrical, mechanical, software and safety characteristics.
The absolute calibration of the dosimetry system is not checked during a type test according
to this standard as only system properties are of interest. The absolute calibration is checked
during a routine test.
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.
IEC 60050-300:2001, International Electrotechnical Vocabulary (IEV) – Electrical and
electronic measurements and measuring instruments – Part 311: General terms relating to
measurements – Part 312: General terms relating to electrical measurements – Part 313:
Types of electrical measuring instruments – Part 314: Specific terms according to the type of
instrument
IEC 60050-393:2003, International Electrotechnical Vocabulary (IEV) – Part 393: Nuclear
instrumentation: Physical phenomena and basic concepts
IEC 60050-394:1995, International Electrotechnical Vocabulary (IEV) – Chapter 394: Nuclear
instrumentation: Instruments
Amendment 1 (1996)
Amendment 2 (2000)
IEC 60068-2-32, Environmental testing – Part 2: Tests. Test Ed: Free fall
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 61000-4-11, 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 4037-1:1996, X and gamma reference radiation for calibrating dosemeters and doserate
meters and for determining their response as a function of photon energy – Part 1: Radiation
characteristics and production methods

62387-1 © IEC:2007 – 11 –
ISO 4037-2:1997, X and gamma reference radiation for calibrating dosemeters and doserate
meters and for determining their response as a function of photon energy – Part 2: Dosimetry
for radiation protection over the energy ranges 8 keV to 1,3 MeV and 4 MeV to 9 MeV
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 4037-4:2004, X and gamma reference radiation for calibrating dosemeters and doserate
meters and for determining their response as a function of photon energy – Part 4: Calibration
of area and personal dosemeters in low energy X reference radiation fields
ISO 6980-1:2006, Nuclear energy – Reference beta-particle radiation – Part 1: Methods of
production
ISO 6980-2:2004, Nuclear energy – Reference beta-particle radiation – Part 2: Calibration
fundamentals related to basic quantities characterizing the radiation field
ISO 6980-3:2006, Nuclear energy – Reference beta-particle radiation – Part 3: Calibration of
area and personal dosemeters and the determination of their response as a function of beta
radiation energy and angle of incidence
ISO 8529-1:2001, Reference neutron radiations – Part 1: Characteristics and methods of
production
ISO 8529-2:2000, Reference neutron radiations – Part 2: Calibration fundamentals of
radiation protection devices related to the basic quantities characterizing the radiation field
ISO 8529-3:1998, Reference neutron radiations – Part 3: Calibration of area and personal
dosimeters and determination of response as a function of energy and angle of incidence
3 Terms and definitions
For the purposes of this document, the following terms and definitions apply.
For definitions related to measurements in general, definitions were taken from
IEC 60050-300, Part 311, from IEC 60050-393 and from IEC 60050-394. A very limited
number of definitions was taken from ISO 4037-3 and the ISO Guide to the Expression of
Uncertainty in Measurement (GUM).
The references are given in brackets [ ]. The information following the brackets is specific to
this standard and is not originating from the given source.
A word between parentheses ( ) in the title of a definition is a qualifier that may be skipped if
there is no danger of confusion with a similar term.

– 12 – 62387-1 © IEC:2007
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
[ICRU 51]
NOTE The recommended depth, d, for environmental monitoring in terms of H*(d) is 10 mm, and H*(d) may be
written as H*(10). [IEV 393-14-95]
3.2
calibration factor
N
quotient of the conventional true value of a quantity C and the indicated value G at the
r,0 r,0
point of test for a reference radiation under reference conditions. It is expressed as
C
r,0
N =
G
r,0
NOTE 1 The reciprocal of the calibration factor is equal to the response under reference conditions. In contrast to
the calibration factor, which refers to the reference conditions only, the response refers to any conditions prevailing
at the time of measurement.
[ISO 4037-3, Definition 3.2.12, modified]
NOTE 2 This definition is of special importance for non-linear dosemeters.
NOTE 3 The reference value C for the dose is given in Table 2.
r,0
3.3
coefficient of variation
v
ratio of the standard deviation s to the arithmetic mean G of a set of n indicated values G
j
(indicated value) given by the following formula:
n
s 1 1 2
v = = ()G − G
∑ j
n −1
G G
j=1
[IEV 394-20-14, modified]
3.4
conventional true value (of a quantity)
C
value attributed to a particular quantity and accepted, sometimes by convention, as having an
uncertainty appropriate for a given purpose
NOTE "Conventional true value" is sometimes called “assigned value”, “best estimate of the value”, “conventional
value” or “reference value”.
[IEV 311-01-06; GUM B.2.4]
62387-1 © IEC:2007 – 13 –
3.5
correction for non-linearity
r
n
quotient of the response R under conditions where only the value of the dose equivalent is
n
varied, and the reference response R . It is expressed as
R
n
r =
n
R
NOTE For a linear dosimetry system, r is equal to unity.
n
3.6
coverage factor
k
numerical factor used as a multiplier of the combined standard uncertainty in order to obtain
an expanded uncertainty
NOTE 1 A coverage factor k is typically in the range 2 to 3.
[GUM 2.3.6]
NOTE 2 In case of a normal distribution, using a coverage factor of 2 results in an expanded uncertainty that
defines an interval around the result of a measurement that contains approximately 95 % of the distribution of
values that could reasonably be attributed to the measurand. For other distributions, the coverage factor may be
larger.
3.7
detector
element of equipment or a substance which, in the presence of radiation, provides a signal for
use in measuring one or more quantities of the incident radiation

[IEV 394-04-01]
NOTE 1 The detector usually requires a separate reader to read out the signal. That means the detector usually is
not able to provide a signal without any external reading process.
NOTE 2 A passive detector does not need an external power supply to collect and store dose information.
NOTE 3 In IEV, the term reads “radiation detector”.
3.8
deviation
D
difference between the indicated values for the same value of the measurand of a dosimetry
system, when an influence quantity assumes, successively, two different values
[IEV 311-07-03, modified]
D = G – G
r
where
G the indicated value under the effect, and
G the indicated value under reference conditions
r
NOTE 1 The original term in IEV 311-07-03 reads “variation (due to an influence quantity)”. In order not to mix up
variation (of the indicated value) and variation of the response, in this standard, the term is called “deviation”.
NOTE 2 The deviation can be positive or negative resulting in an increase or a decrease of the indicated value,
respectively.
– 14 – 62387-1 © IEC:2007
3.9
dosemeter
radiation meter designed to measure the quantities absorbed dose or dose equivalent
NOTE 1 In a wider sense, this term is used for meters designed to measure other quantities related to radiation
such as exposure, fluence, etc. Such use is deprecated.
NOTE 2 This apparatus may require a separate reader to read out the absorbed dose or dose equivalent.
[IEV 394-02-11]
NOTE 3 A dosemeter usually consists of a detector and a badge, for example TLD badge with filters.
3.10
dosimetry system
dosemeter, reader and all associated equipment and procedures used for assessing the
indicated value
[IEV 394-11-06, modified]
3.11
expanded uncertainty
U
quantity defining an interval about the result of a measurement that may be expected to
encompass a large fraction of the distribution of values that could reasonably be attributed to
the measurand
[GUM 2.3.5]
NOTE 1 The expanded uncertainty is obtained by multiplying the combined standard uncertainty by a coverage
factor.
NOTE 2 In this standard, the confidence level is 95 %.
3.12
indicated value
G
value of the measurand given directly by a measuring instrument on the basis of its calibration
curve
[IEV 311-01-08]
NOTE 1 In this standard, the indicated value is the one given by the dosimetry systems as the final result of the
evaluation algorithm (for example display of the software, print out) in units of dose equivalent (Sv), see 8.2.
NOTE 2 The indicated value is equivalent to the evaluated value in ISO 12794, Annex D.
NOTE 3 For details, see Annex B of this standard.
3.13
influence quantity
quantity that is not the measurand but that affects the result of the measurement
NOTE 1 For example, temperature of a micrometer used to measure length.
[IEV 394-20-27; GUM B.2.10]
62387-1 © IEC:2007 – 15 –
NOTE 2 If the effect on the result of a measurement of an influence quantity depends on another influence
quantity, these influence quantities are treated as a single one. In this standard, this is the case for two pairs of
influence quantities:
1 – radiation energy and angle of incidence,
2 – ambient temperature and relative humidity.
3.14
influence quantity of type F
influence quantity whose effect on the indicated value is a change in response
NOTE 1 An example is radiation energy and angle of radiation incidence.
NOTE 2 F stands for factor. The indication due to radiation is multiplied by a factor due to the influence quantity.
3.15
influence quantity of type S
influence quantity whose effect on the indicated value is a deviation independent of the
indicated value
NOTE 1 An example is the electromagnetic disturbance.
NOTE 2 All requirements for influence quantities of type S are given with respect to the value of the deviation D.
NOTE 3 S stands for sum. The indication is the sum of the indication due to radiation and due to the disturbance.
3.16
lower limit of the measuring range
H
low
lowest dose value included in the measuring range
3.17
maximum rated measurement time
t
max
longest continuous period of time over which the dose is accumulated and over which all
requirements of this standard are fulfilled
NOTE 1 The maximum rated measuring time depends on the lower limit of the measuring range H , the fading,
low
etc.
NOTE 2 The beginning of this period of time can for example be erasing the dose by heating (at TLDs) or a dose
reset by means of software (at DIS).
3.18
measured value
M
value that can be obtained from the indicated value G by applying the model function for the
measurement
NOTE 1 The uncertainty model function combines the indicated value G with the reference calibration factor N ,
the correction for non-linearity r , the l deviations D (p = 1.l) for the influence quantities of type S, and the m
n p
relative response values r (q = 1.m) for the influence quantities of type F:
q
l
⎡ ⎤
N
⎢ ⎥
M = G − D .
∑ p
m
⎢ ⎥
p=1
⎣ ⎦
r r
n q

q=1
This uncertainty model function is necessary to evaluate the uncertainty of the system according to the GUM (see
GUM sections 3.1.6, 3.4.1 and 4.1).
NOTE 2 For “model” function, see Note 2 to 3.35.
NOTE 3 The calculations according to this model function are usually not performed, only in the case that specific
influence quantities are well known and an appropriate correction is applied.

– 16 – 62387-1 © IEC:2007
NOTE 4 If necessary, another model function closer to the design of a certain dosimetry system may be used.
NOTE 5 For details, see Annex B.
3.19
measuring range
range defined by two values of the measurand, or quantity to be supplied, within which the
limits of uncertainty of the measuring instrument are specified
[IEV 311-03-12]
NOTE In this standard, the measuring range is the range of dose equivalent, in which the requirements of this
standard are fulfilled and thus the uncertainty is limited.
3.20
minimal rated range (of use)
smallest range being specified for an influence quantity or instrument parameter over which
the dosimetry system shall operate in compliance with this standard
NOTE The minimal rated ranges of the influence quantities dealt with in this standard are given in the second
column of Tables 3 to 7.
3.21
personal dose equivalent
H (d)
p
dose equivalent in soft tissue, at an appropriate depth, d, below a specified point on the body
[ICRU 51]
NOTE 1 The recommended depths are 10 mm for penetrating radiation and 0,07 mm for superficial radiation.
[IEV 393-14-97]
NOTE 2 Soft tissue means ICRU 4-element tissue, see ICRU Report 39.
3.22
point of test
point in the radiation field at which the conventional true value of the quantity to be measured
is known
[ISO 4037-3, Definition 3.2.6, modified]
3.23
preparation
normal treatment of dosemeters or detectors before a dose measurement, for example a
procedure to erase stored dose information, reset the dose information by means of software,
cleaning, etc., which the dosemeters or detectors are intended to be subjected to in routine
use
3.24
rated range (of use)
specified range of values which an influence quantity can assume without causing a deviation
or variation of the response exceeding specified limits
[IEV 311-07-05, modified]
NOTE 1 In IEV 311-07-05, the term reads “nominal range of use”. In this standard, “rated range” is used in order
to avoid complicated terms like “the range of use of an influence quantity” but to have terms that are easily
readable like “the rated range of an influence quantity”.
NOTE 2 Influence quantities can be either of type S or of type F.
3.25
reader
instrument designed to read out one or more detectors in a dosemeter

62387-1 © IEC:2007 – 17 –
[IEV 394-11-10, modified]
NOTE 1 Signal of a passive dosimeter can be amount of light, amount of charge, transparency of film and so on.
Each type of passive dosimeter thus has very a different type of reader.
NOTE 2 In IEV, the term reads “dosemeter reader”.
3.26
readout
process of measuring the stored dose information of a detector in a reader.
3.27
reference conditions
set of specified values and/or ranges of values of influence quantities under which the
uncertainties admissible for a dosimetry system are the smallest
[IEV 311-06-02, modified]
3.28
reference direction
direction, in the coordinate system of a dosemeter, with respect to which the angle to the
direction of radiation incidence is measured in unidirectional fields
[ISO 4037-3, 3.2.7]
3.29
reference orientation
(dosemeter) orientation for which the direction of the incident radiation coincides with the
reference direction of the dosemeter
[ISO 4037-3, 3.2.8]
3.30
reference point of a dosemeter
physical mark or marks on the outside of the dosemeter to be used in order to position it with
respect to the point of test
[IEV 394-20-15, modified]
3.31
reference response
R
response for a reference value C of the quantity to be measured under reference conditions
r,0
G
r,0
R =
C
r,0
where G is the corresponding indicated value
r,0
NOTE 1 The reference response is the reciprocal of the reference calibration factor.
NOTE 2 The reference values for the dose are given in Table 2.
3.32
relative expanded uncertainty
U
rel
expanded uncertainty divided by the measurement result

– 18 – 62387-1 © IEC:2007
3.33
relative response
r
quotient of the response R and the reference response R
R
r =
R
3.34
response (of a radiation measuring assembly)
R
ratio, under specified
...

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