EN 61005:2017

SLOVENSKI STANDARD
01-april-2017
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SIST EN 61005:2005
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Radiation protection instrumentation - Neutron ambient dose equivalent (rate) meters
(IEC 61005:2014)
Strahlenschutz-Messgeräte - Umgebungsäquivalentdosis(leistungs)-Messgeräte für
Neutronenstrahlung (IEC 61005:2014)
Instrumentation pour la radioprotection - Appareils de mesure de l'équivalent de dose
ambiant neutron (ou de son débit d'équivalent de dose) (IEC 61005:2014)
Ta slovenski standard je istoveten z: EN 61005:2017
ICS:
13.280 Varstvo pred sevanjem Radiation protection
17.240 Merjenje sevanja Radiation measurements
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega standarda ni dovoljeno.

EUROPEAN STANDARD EN 61005
NORME EUROPÉENNE
EUROPÄISCHE NORM
January 2017
ICS 13.280 Supersedes EN 61005:2004
English Version
Radiation protection instrumentation - Neutron ambient dose
equivalent (rate) meters
(IEC 61005:2014 , modified)
Instrumentation pour la radioprotection - Appareils de Strahlenschutz-Messgeräte -
mesure de l'équivalent de dose ambiant neutron (ou de son Umgebungsäquivalentdosis(leistungs)-Messgeräte für
débit d'équivalent de dose) Neutronenstrahlung
(IEC 61005:2014 , modifiée) (IEC 61005:2014 , modifiziert)
This European Standard was approved by CENELEC on 2016-11-14. CENELEC 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 CENELEC 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 CENELEC member into its own language and notified to the CEN-CENELEC Management Centre has the
same status as the official versions.
CENELEC members are the national electrotechnical committees of Austria, Belgium, Bulgaria, Croatia, Cyprus, the Czech Republic,
Denmark, Estonia, Finland, Former Yugoslav Republic of Macedonia, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Latvia,
Lithuania, Luxembourg, Malta, the Netherlands, Norway, Poland, Portugal, Romania, Serbia, Slovakia, Slovenia, Spain, Sweden,
Switzerland, Turkey and the United Kingdom.

European Committee for Electrotechnical Standardization
Comité Européen de Normalisation Electrotechnique
Europäisches Komitee für Elektrotechnische Normung
CEN-CENELEC Management Centre: Avenue Marnix 17, B-1000 Brussels
© 2017 CENELEC All rights of exploitation in any form and by any means reserved worldwide for CENELEC Members.
Ref. No. EN 61005:2017 E
European foreword
This document (EN 61005:2017) consists of the text of IEC 61005:2014 prepared by
SC 45B “Radiation protection instrumentation” of IEC/TC 45 “Nuclear instrumentation”, together with
the common modifications prepared by CLC/TC 45B "Radiation protection instrumentation".

The following dates are fixed:

(dop) 2017-11-14
• latest date by which the document has to be
implemented at national level
by publication of an identical
national standard or by endorsement
(dow) 2019-11-14
• latest date by which the national standards conflicting
with the document have to be withdrawn

This document supersedes EN 61005:2004.

Attention is drawn to the possibility that some of the elements of this document may be the subject of
patent rights. CENELEC [and/or CEN] shall not be held responsible for identifying any or all such
patent rights.
Endorsement notice
The text of the International Standard IEC 61005:2014 was approved by CENELEC as a European
Standard with agreed common modifications.
COMMON MODIFICATIONS
1 Scope
In the note, replace “realistic field” with “workplace field” twice.

3 Terms and definitions, abbreviations and symbols, quantities and units
3.1 Terms and definitions
3.1.17
minimal rated range of use
Replace “minimal” with “minimum” (in the term an in the note).

6 Radiation detection requirements
6.4 Variation of the response due to neutron energy
6.4.2 Requirements
In the first paragraph, delete “at least” twice.
And, add a dot above the H in the second term r .
H*(10)
6.4.3 Test method
In the second paragraph, add at the end of item b) “(one of them 144 keV)”.
252 241
And in item c), replace “one broad source (e.g. Cf or Am-Be)” with “two broad sources
252 252 241
(D2O-moderated Cf and e.g. Cf or Am-Be)”.
Replace the fourth paragraph starting with “The test distance should be at least 3 times …”
with “The test distance should be at least 3 times the sum of the largest linear dimension of
the source and the detector. In case of neutron fields according to ISO 8529, the scatter
contribution to the indicated value shall be determined in compliance with ISO 8529-2 and the
indicated value shall be corrected for scattered neutrons.”
In the note, replace “realistic work place” with “workplace”.

6.6 Variation of the response due to angle of incidence
6.6.3 Test method
Replace the fourth and fifth sentence starting with “The scatter contribution to the indicated
value …” with “In case of neutron fields according to ISO 8529, the scatter contribution to the
indicated value shall be determined in compliance with ISO 8529-2 and the indicated value
shall be corrected for scattered neutrons.”

6.13 Response to other external ionizing radiations
Replace the paragraph by “If the detector’s cover does not shield alpha and beta radiation,
the response due to alpha and beta radiation should be measured – and the results should be
documented.”
7 Additivity of indicated value
7.2 Test method
H +−HH
iK iL
iK+L
( )
Replace the equation with ∆=H
imix
H
iK+L
( )
9 Electrical characteristics
9.3 Power supplies – battery operation
9.3.3 Test method
9.3.3.3 Test using power supply
9.3.3.3.3 Interpretation of the results
Replace “0,91” with “0,9”.
Table 1 – Reference conditions and standard test conditions
In the first line (Reference neutron radiation), replace “L(p,n)” with “Li(p,n)” twice.

Table 2 – Radiation characteristics of ambient neutron dose (rate) equivalent meters
In the fourth line (Overload), replace “until unit is reset of switched off” with “until unit is reset
or is switched off”.
Annex ZA
(normative)
Normative references to international publications
with their corresponding European publications

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.

NOTE 1 When an International Publication has been modified by common modifications, indicated by (mod), the relevant
EN/HD applies.
NOTE 2 Up-to-date information on the latest versions of the European Standards listed in this annex is available here:
www.cenelec.eu
Publication Year Title EN/HD Year

IEC 60050 Series International Electrotechnical Vocabulary - -
1)
IEC 60086-1 2011 Primary batteries - EN 60086-1 2011
Part 1: General
2)
IEC 60086-2 2011 Primary batteries - EN 60086-2 2011
Part 2: Physical and electrical
specifications
IEC 60529 -  Degrees of protection provided by EN 60529 -
enclosures (IP Code)
IEC 61187 -  Electrical and electronic measuring EN 61187 -
equipment - Documentation
IEC 62706 -  Radiation protection instrumentation - - -
Environmental, electromagnetic and
mechanical performance requirements
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
1)
Superseded by EN 60086-1:2015 (IEC 60086-1:2015): DOW=2018-09-01.
2)
Superseded by EN 60086-2:2016 (IEC 60086-2:2015): DOW=2018-12-03.
Publication Year Title EN/HD Year

ISO 11929 2010 Determination of the characteristic limits - -
(decision threshold, detection limit and
limits of the confidence interval) for
measurements of ionizing radiation -
Fundamentals and application
ISO 12789-1 2008 Reference radiation fields - Simulated - -
workplace neutron fields -
Part 1: Characteristics and methods of
production
ISO 12789-2 2008 Reference radiation fields - Simulated - -
workplace neutron fields -
Part 2: Calibration fundamentals related to
the basic quantities
IEC 61005 ®
Edition 3.0 2014-07
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
Radiation protection instrumentation – Neutron ambient dose equivalent

(rate) meters
Instrumentation pour la radioprotection – Appareils de mesure de l'équivalent

de dose ambiant neutron (ou de son débit d'équivalent de dose)

INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
COMMISSION
ELECTROTECHNIQUE
PRICE CODE
INTERNATIONALE
CODE PRIX XA
ICS 13.280 ISBN 978-2-8322-1676-7

– 2 – IEC 61005:2014 © IEC 2014
CONTENTS
FOREWORD . 6
1 Scope . 8
2 Normative references . 8
3 Terms and definitions, abbreviations and symbols, quantities and units . 9
3.1 Terms and definitions. 9
3.2 Test nomenclature . 15
3.3 Abbreviations and symbols . 15
3.4 Quantities and units . 16
4 General test procedure . 16
4.1 Test requirements . 16
4.2 Tests performed with variation of influence quantities . 16
4.2.1 General . 16
4.2.2 Tests for influence quantities of type F . 16
4.2.3 Tests for influence quantities of type S . 17
4.3 Consideration of non-linearity . 17
4.4 Consideration of several detectors or signals in a dose (rate) meter . 17
4.5 Statistical fluctuations . 17
4.6 Radiation sources . 17
4.7 Work place neutron fields . 18
5 General requirements . 18
5.1 Summary of requirements . 18
5.2 General characteristics . 18
5.2.1 Effective range of measurement . 18
5.2.2 Minimum range of measurement . 19
5.2.3 Rated range of an influence quantity . 19
5.2.4 Minimum rated range of influence quantity . 19
5.2.5 Indication of the assembly . 19
5.3 Mechanical characteristics . 19
5.3.1 IP classification . 19
5.3.2 Assembly labels and markings . 19
5.3.3 Ease of decontamination . 20
5.4 Interface requirements . 20
5.5 Algorithm to evaluate the indicated value . 20
6 Radiation detection requirements . 20
6.1 General . 20
6.2 Consideration of the uncertainty of the conventional quantity value . 20
6.3 Constancy of the dose rate response, dose dependence and statistical
fluctuations . 20
6.3.1 General . 20
6.3.2 Requirements . 21
6.3.3 Test method using sources . 21
6.3.4 Interpretation of the results of the test using sources . 21
6.3.5 Test procedure with variation of the calibration distance . 21
6.3.6 Equivalent electrical test method . 22
6.3.7 Interpretation of the equivalent electrical test results . 22
6.4 Variation of the response due to neutron energy . 22

IEC 61005:2014 © IEC 2014 – 3 –
6.4.1 General . 22
6.4.2 Requirements . 23
6.4.3 Test method . 23
6.4.4 Interpretation of the results . 24
6.5 Monte Carlo calculation of the instrument response . 24
6.5.1 General . 24
6.5.2 Requirements . 24
6.5.3 Test method . 24
6.5.4 Interpretation of the results . 24
6.6 Variation of the response due to angle of incidence . 25
6.6.1 General . 25
6.6.2 Requirements . 25
6.6.3 Test method . 25
6.6.4 Interpretation of the results . 25
6.7 Overload characteristics . 25
6.7.1 Dose equivalent meters . 25
6.7.2 Dose rate equivalent meters . 26
6.8 Response time . 26
6.8.1 Requirements . 26
6.8.2 Test method . 27
6.8.3 Interpretation of the results . 27
6.9 Relationship between response time and statistical fluctuations . 27
6.10 Dose equivalent rate alarm . 28
6.10.1 Requirements . 28
6.10.2 Test method . 28
6.10.3 Interpretation of the results . 28
6.11 Dose equivalent alarm . 28
6.11.1 Requirements . 28
6.11.2 Test method . 28
6.11.3 Interpretation of the results . 28
6.12 Response to photon radiation . 29
6.12.1 Requirements . 29
6.12.2 Test method . 29
6.12.3 Interpretation of the results . 29
6.13 Response to other external ionizing radiations . 29
7 Additivity of indicated value . 30
7.1 Requirements . 30
7.2 Test method . 30
7.3 Interpretation of the results . 30
8 Software . 31
8.1 General . 31
8.2 Requirements . 31
8.2.1 General requirements . 31
8.2.2 Design and structure of the software. 31
8.2.3 Protection of the software and data . 31
8.2.4 Documentation . 32
8.3 Test method . 32
8.3.1 General . 32
8.3.2 Testing the documentation . 32

– 4 – IEC 61005:2014 © IEC 2014
9 Electrical characteristics . 33
9.1 Stability of zero indication with time . 33
9.1.1 Requirements . 33
9.1.2 Test method . 33
9.1.3 Interpretation of the results . 33
9.2 Warm-up time . 33
9.2.1 Requirements . 33
9.2.2 Test method . 33
9.2.3 Interpretation of the results . 33
9.3 Power supplies – battery operation . 33
9.3.1 General . 33
9.3.2 Requirements . 34
9.3.3 Test method . 34
9.4 Power supplies – Mains operations . 35
9.4.1 Requirements . 35
9.4.2 Test method . 35
9.4.3 Interpretation of the results . 36
10 Environmental requirements . 36
10.1 General . 36
10.2 Ambient temperature . 36
10.3 Temperature shock . 36
10.4 Relative humidity . 37
10.5 Atmospheric pressure . 37
10.6 Protection against moisture and dust (IP classification) . 37
10.7 Storage and transport . 37
11 Mechanical requirements . 37
11.1 General . 37
11.2 Drop test . 38
11.3 Vibration test . 38
11.4 Microphonics impact . 38
11.5 Mechanical shock . 38
12 Electromagnetic requirements . 39
12.1 General . 39
12.2 Emission of electromagnetic radiation . 39
12.3 Electrostatic discharge . 39
12.4 Radio frequency disturbance . 39
12.5 Magnetic fields . 39
12.6 Alternating current powered equipment requirements . 40
13 Documentation . 40
13.1 Operation and maintenance manual . 40
13.2 Identification certificate . 40
13.3 Type test report . 41
Annex A (informative) Neutron fluence-to-ambient dose equivalent conversion
coefficients . 47
Bibliography . 50

Figure A.1 – Neutron fluence-to-ambient dose equivalent conversion coefficients for
mono-energetic neutrons [5] . 48

IEC 61005:2014 © IEC 2014 – 5 –

Table 1 – Reference conditions and standard test conditions . 41
Table 2 – Radiation characteristics of ambient neutron dose (rate) equivalent meters . 42
Table 3 – Values of c and c for w different dose rate values and n indications for
1 2
each dose rate value [8] . 43
Table 4 – Electrical and environmental characteristics of ambient dose equivalent
(rate) meters . 44
Table 5 – Maximum values of deviation due to mechanical requirements . 44
Table 6 – Maximum values of deviation due to electromagnetic disturbances . 45
Table 7 – Emission frequency range . 45
Table 8 – Symbols and abbreviations used in this standard . 46
Table A.1 – Neutron fluence-to-ambient dose equivalent conversion coefficients for
mono-energetic neutrons ([5],[6]) . 47
Table A.2 – Neutron fluence-to-ambient dose equivalent conversion coefficients for
the neutron reference radiation sources ([5] and ISO 8529-3) . 49

– 6 – IEC 61005:2014 © IEC 2014
INTERNATIONAL ELECTROTECHNICAL COMMISSION
____________
RADIATION PROTECTION INSTRUMENTATION –
NEUTRON AMBIENT DOSE EQUIVALENT (RATE) METERS

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
this end and in addition to other activities, IEC publishes International Standards, Technical Specifications,
Technical Reports, Publicly Available Specifications (PAS) and Guides (hereafter referred to as “IEC
Publication(s)”). Their preparation is entrusted to technical committees; any IEC National Committee interested
in the subject dealt with may participate in this preparatory work. International, governmental and non-
governmental organizations liaising with the IEC also participate in this preparation. IEC collaborates closely
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
consensus of opinion on the relevant subjects since each technical committee has representation from all
interested IEC National Committees.
3) IEC Publications have the form of recommendations for international use and are accepted by IEC National
Committees in that sense. While all reasonable efforts are made to ensure that the technical content of IEC
Publications is accurate, IEC cannot be held responsible for the way in which they are used or for any
misinterpretation by any end user.
4) In order to promote international uniformity, IEC National Committees undertake to apply IEC Publications
transparently to the maximum extent possible in their national and regional publications. Any divergence
between any IEC Publication and the corresponding national or regional publication shall be clearly indicated in
the latter.
5) IEC itself does not provide any attestation of conformity. Independent certification bodies provide conformity
assessment services and, in some areas, access to IEC marks of conformity. IEC is not responsible for any
services carried out by independent certification bodies.
6) All users should ensure that they have the latest edition of this publication.
7) No liability shall attach to IEC or its directors, employees, servants or agents including individual experts and
members of its technical committees and IEC National Committees for any personal injury, property damage or
other damage of any nature whatsoever, whether direct or indirect, or for costs (including legal fees) and
expenses arising out of the publication, use of, or reliance upon, this IEC Publication or any other IEC
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 61005 has been prepared by subcommittee 45B: Radiation protection
instrumentation, of IEC technical committee 45: Nuclear instrumentation.
This third edition cancels and replaces the second edition of IEC 61005 issued in 2003 and
constitutes a technical revision.
This edition includes the following significant technical changes with respect to the previous
edition:
a) upper neutron energy of the instruments covered by the standard is increased to 20 MeV;
b) requirement for the variation of the relative response due to neutron energy is modified;
c) a clause for additivity of the indicated value (neutron dose/dose rate) is introduced;
d) a clause and requirement for Monte Carlo calculation of the instrument response are
introduced;
e) a clause and requirement for the software for generation of the measured values are
introduced;
f) environmental testing methods and requirements are referred to IEC 62706;

IEC 61005:2014 © IEC 2014 – 7 –
g) influence quantities of type S and F are introduced.
The text of this standard is based on the following documents:
FDIS Report on voting
45B/792/FDIS 45B/797/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.
– 8 – IEC 61005:2014 © IEC 2014
RADIATION PROTECTION INSTRUMENTATION –
NEUTRON AMBIENT DOSE EQUIVALENT (RATE) METERS

1 Scope
This International Standard is applicable to assemblies designed to measure the ambient
dose equivalent (rate) due to neutron radiation in fields that contain neutrons with energies
below 20 MeV, and which comprise at least:
a) a detection assembly, which may, for example, consist of a detector probe for thermal
neutrons and an arrangement of neutron moderating and absorbing media surrounding the
detector;
b) a measuring assembly with a display for the measured quantity, which may be
incorporated into a single assembly with the detector or connected to it by means of a
flexible cable.
Instruments with energy range up to 20 MeV are covered by this standard. If the instrument
also provides indication of the neutron dose, it should meet the neutron dose requirements
stated in this standard.
No tests are specified in this standard for performance requirements of assemblies in pulsed
radiation fields. It is understood that an assembly designed to meet this standard may not be
suitable for use in such fields.
The object of this standard is to specify requirements for the performance characteristics of
neutron ambient dose equivalent (rate) meters, and to prescribe the methods of testing in
order to determine compliance with this standard. This standard specifies general
characteristics, general test procedures, radiation characteristics, electrical, mechanical,
safety and environmental characteristics, and also the identification certificate (see 13.2).
Requirements and test procedures are also specified for the alarm performance of the neutron
ambient dose equivalent (rate) meters, equipped with alarm provisions.
NOTE The response of ambient dose equivalent (rate) meters for neutrons is energy dependent and may
deviate considerably from unity. The response in realistic neutron fields, however, is such that the
response deviations in different energy ranges tend to offset each other. Consequently, the response in
realistic fields is generally much closer to unity.
ISO 12789 specifies a list of appropriate broad-spectrum neutron sources that are suitable for the testing
of such (rate) meters. For example, simulated workplace neutron fields from ISO 12789 may be specified by
agreement between manufacturer and purchaser to be appropriate for testing when the spectral environment is well
defined.
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 60050 (all parts): International Electrotechnical Vocabulary (available at
http://www.electropedia.org)
IEC 60086-1:2011, Primary batteries – Part 1: General
IEC 60086-2:2011, Primary batteries – Part 2: Physical and electrical specifications

IEC 61005:2014 © IEC 2014 – 9 –
IEC 60529, Degrees of protection provided by enclosures (IP Code)
IEC 61187, Electrical and electronic measuring equipment – Documentation
IEC 62706, Radiation protection instrumentation – Environmental, electromagnetic and
mechanical requirements
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 characterising the radiation field
ISO 8529-3:1998, Reference neutron radiations – Part 3: Calibration of area and personal
dosemeters and determination of response as a function of energy and angle of incidence
ISO 11929:2010, Determination of the characteristic limits (decision threshold, detection limit
and limits of the confidence interval) for measurements of ionizing radiation – Fundamentals
and application
ISO 12789-1:2008, Reference radiation fields – Simulated workplace neutron fields – Part 1:
Characteristics and methods of production
ISO 12789-2:2008, Reference radiation fields – Simulated workplace neutron fields – Part 2:
Calibration fundamentals related to basic quantities
3 Terms and definitions, abbreviations and symbols, quantities and units
3.1 Terms and definitions
For the purposes of this document, the following terms and definitions, as well as those given
in IEC 60050-395 apply.
NOTE For sentence clarity and text conciseness in this standard the term “neutron ambient dose equivalent
(rate) meter” is abbreviated as “neutron dose (rate) meter”. Whenever the term “neutron dose (rate) meter” appears
in this standard it is understood that “neutron ambient dose equivalent (rate) meter” is meant.
3.1.1
alarm
audible, visual, or other signal activated when the instrument reading exceeds a preset value,
falls outside of a preset range, when the instrument is unable to function properly (component
failure), or when the instrument detects the presence of the source of radiation according to a
preset condition
3.1.2
ambient dose equivalent
H*(10)
dose equivalent at a point in a radiation field that would be produced by the corresponding
aligned and expanded field, in the ICRU sphere at a depth of 10 mm on the radius opposing
the direction of the aligned field ([2], [5] )
Note 1 to entry: An instrument that has an isotropic response and is calibrated in terms of H*(10) will measure
H*(10) in a radiation field that is uniform over the dimensions of the instrument.
________________
Numbers in square brackets refer to the Bibliography.

– 10 – IEC 61005:2014 © IEC 2014
3.1.3
ambient dose equivalent rate
H*(10)
ratio of dH*(10) by dt, where 𝑑𝐻*(10) is the increment of ambient dose equivalent in the time
interval dt
∗
𝑑𝐻 (10)
∗̇
𝐻 (10) =
𝑑𝑡
3.1.4
background level
radiation field in which the instrument is intended to operate, including that produced by
naturally occurring radioactive material and cosmic radiation
3.1.5
calibration distance
distance between the reference point of the assembly and the centre of the calibration source
3.1.6
coefficient of variation
v
�
ratio of the experimental standard deviation s to the arithmetic mean 𝐻 of a set of n
H . It is given by the following formula:
indications
j
𝑠 1 1
𝑛
�
v= = .� .∑ (𝐻−𝐻)
𝑗
𝑗=1
� �
𝐻 𝐻 𝑛−1
3.1.7
conventional quantity value
H
t
quantity value attributed by agreement to a quantity for a given purpose
Note 1 to entry: In this standard the quantity is the dose equivalent (rate).
Note 2 to entry: The term “conventional true quantity value” is sometimes used for this concept.
Note 3 to entry: Sometimes a conventional quantity value is an estimate of a true quantity value.
Note 4 to entry: A conventional quantity value is generally accepted as being associated with a suitably small
measurement uncertainty, which might be zero.
[SOURCE: VIM:2008, 2.12]
3.1.8
deviation
D
difference between the indicated values for the same value of the measurand of a dose equi-
valent (rate) meter, when made under reference conditions and when subject to an influence
quantity
D = H – H
i r
Where
is the indicated value under the effect of an influence quantity, and
H
i
H is the indicated value under reference conditions.
r
Note 1 to entry: The deviation can be positive or negative resulting in an increase or a decrease of the indicated
value, respectively.
Note 2 to entry: The deviation is of special importance for influence quantities of Type S.

IEC 61005:2014 © IEC 2014 – 11 –
3.1.9
effective range of measurement
range of values of ambient dose equivalent (rate) over which the performance of the ambient
dose equivalent (rate) meter meets the requirements of this standard
3.1.10
indicated value
H
i
value given by the (digital) indication of the dose (rate) meter in units of dose equivalent or
dose equivalent rate
3.1.11
influence quantity
quantity that is not the measurand but that affects the result of the measurement
Note 1 to entry: For example, temperature of a micrometer used to measure length.
Note 2 to entry: 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.
[SOURCE: IEC 60050-394:2007,394-40-27]
3.1.12
influence quantity of type F
influence quantity whose effect on the indicated value is a change in response
Note 1 to entry: An example is radiation energy and angle of radiation incidence.
Note 2 to entry: “F” stands for factor: The indication due to radiation is multiplied by a factor due to the influence
quantity.
3.1.13
influence quantity of type S
influence quantity whose effect on the indicated value is a deviation independent of the
indicated value
Note 1 to entry: An example is the electromagnetic disturbance.
Note 2 to entry: All requirements for influence quantities of type S are given with respect to the value of the
deviation D.
Note 3 to entry: “S” stands for sum. The indication is the sum of the indication due to radiation and due to the
influence quantity, e.g., electromagnetic disturbance.
3.1.14
lower limit of effective range of measurement
H or (𝐻̇)
the lowest dose (rate) value included in the effective range of measurement
3.1.15
maximum dose equivalent rate for dose (rate) meters

H
max
dose rate, specified by the manufacturer, below which the effect of the dose rate on the dose
rate reading is within specified limits
3.1.16
measured value
M
value that can be obtained from th
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