IEC 61005:2014

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)

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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

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

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
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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 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;

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 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.

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 the indicated value H by applying the model function for the
i
measurement
– 12 – IEC 61005:2014 © IEC 2014
Note 1 to entry: The model function is necessary to evaluate the uncertainty of the measured value according to
the GUM (see [3]:2008,3.1.6, 3.4.1 and 4.1).
Note 2 to entry: An example of a model function is given herein. It combines the indicated value H
i
with the reference calibration factor N , the correction for non-linear response r , the l deviations D (p = 1.l) for
0 n p
the influence quantities of type S, and the m relative response values r (q = 1.m) for the influence quantities of

q
type F:
l
 
N
 
M = H − D .
i ∑ p
m
 
p=1
 
r r
n ∏ q
q=1
Note 3 to entry: The calculations according to such model function are usually not performed, only in the case
that specific influence quantities are well known and an appropriate correction is applied.
Note 4 to entry: If necessary another model function closer to the design of a certain dose (rate) meter may be
used.
Note 5 to entry: With the calibration controls adjusted according to the manufacturer’s instructions, the reference
calibration factor, the correction for non-linear response and all relative response values are set to one and the
deviations are set to zero, these settings cause an uncertainty of measurement which can be determined from the
measured variation of the response values and the measured deviations. For a dose (rate) meter tested according
to this standard, all these data are available.
3.1.17
minimal rated range of use
the smallest range being specified for an influence quantity or instrument parameter over
which the dose equivalent (rate) meter shall operate within the specified limits of variation in
order to comply with this standard
Note 1 to entry: The minimal rated ranges of the influence quantities dealt with in this standard are given in the
second column of Tables 2, 4, 5 and 6.
3.1.18
neutron ambient dose equivalent (rate) meter
assembly intended to measure the ambient dose equivalent dose and/or rate from neutron
radiation
3.1.19
neutron dose equivalent response
𝑹
𝐇
ratio, under specified conditions, given by the relation
R
Φ
R =
H
h
Φ
Where
R is the neutron fluence response (see definition 3.1.22) and
Φ
h is the neutron fluence-to-dose conversion coefficient (see definition 3.1.23).
Φ
3.1.20
neutron fluence
Φ
quotient of dN by da, where dN is the number of neutrons incident on a sphere of cross-
sectional area da:
𝑑𝑁
Φ =
𝑑𝑎
–2
Note 1 to entry: The unit of neutron fluence is m .
3.1.21
neutron fluence rate (flux density)
𝛷̇
quotient of dΦ by dt, where dΦ is the increment of neutron fluence in the time interval dt:
𝑑𝛷
𝛷̇ =
𝑑𝑡
–2 –1
Note 1 to entry: The unit of neutron fluence rate is m ∙s .
3.1.22
neutron fluence response
𝑹
𝜱
ratio, under specified conditions, given by the relation
𝑀
𝑅 =
𝛷
𝛷
Where
M is the reading by the instrument under test (dosemeter) for the neutron fluence and
Φ is the conventional quantity value of the neutron fluence to which the instrument has been
exposed.
Note 1 to entry: The unit of neutron fluence response is m .
3.1.23
neutron fluence-to-ambient dose equivalent conversion coefficient
ℎ
𝛷
quotient of the neutron ambient dose equivalent, H*(10), and the neutron fluence, Φ, at a
point in the radiation field, undisturbed by the irradiated object
∗
( )
𝐻 10
ℎ =
𝛷
𝛷
Note 1 to entry: The conversion coefficients are given in Annex A.
3.1.24
non-linearity
variation of the value of the (relative) response with the dose (rate) being measured
3.1.25
point of test of a dose (rate) equivalent meter
point at which the conventional quantity value is determined and at which the reference point
of the dose equivalent (rate) meter is placed for calibration and test purposes
Note 1 to entry: For all tests involving the use of radiation, the reference point of the assembly is placed at the
point of test in the orientation indicated by the manufacturer. An exception is the test of variation in
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