IEC 61322:2020

IEC 61322 ®
Edition 2.0 2020-01
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
Radiation protection instrumentation – Installed ambient dose equivalent rate
meters, warning and monitoring assemblies for neutrons with energies from
thermal to 20 MeV
Instrumentation pour la radioprotection – Débitmètres d'équivalent de dose
ambiant, ensembles d'alarmes et moniteurs à poste fixe pour des énergies de
neutrons comprises entre l'énergie thermique et 20 MeV

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IEC 61322 ®
Edition 2.0 2020-01
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
Radiation protection instrumentation – Installed ambient dose equivalent rate

meters, warning and monitoring assemblies for neutrons with energies from

thermal to 20 MeV
Instrumentation pour la radioprotection – Débitmètres d'équivalent de dose

ambiant, ensembles d'alarmes et moniteurs à poste fixe pour des énergies de

neutrons comprises entre l'énergie thermique et 20 MeV

INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
COMMISSION
ELECTROTECHNIQUE
INTERNATIONALE
ICS 13.280; 17.240 ISBN 978-2-8322-7635-8

– 2 – IEC 61322:2019  IEC 2019
CONTENTS
FOREWORD . 6
1 Scope . 8
2 Normative references . 9
3 Terms and definitions, abbreviated terms and symbols, quantities and units . 10
3.1 Terms and definitions . 10
3.2 Abbreviated terms and symbols . 17
3.3 Quantities and units . 18
4 Design requirements . 18
4.1 Construction and performance . 18
4.1.1 General . 18
4.1.2 Equipment configuration . 18
4.1.3 Equipment reliability . 19
4.2 Indication facilities . 19
4.3 Alarm facilities . 19
4.3.1 General . 19
4.3.2 High level alarms . 20
4.3.3 Low level alarms . 20
4.3.4 Instrument fault alarms . 20
4.4 External facilities . 20
4.5 Effective range of measurement . 20
4.5.1 General . 20
4.5.2 Requirements . 21
4.5.3 Interrelationship between response time and statistical fluctuations . 21
4.5.4 Rated range of an influence quantity. 21
4.5.5 Minimum rated range of influence quantity . 22
4.6 Ingress protection (IP) classification . 22
4.7 Assembly labels and markings . 22
4.8 Functional safety . 22
5 General test procedure . 22
5.1 Test requirements . 22
5.2 Tests performed with variation of influence quantities . 23
5.2.1 General . 23
5.2.2 Tests for influence quantities of type F . 25
5.2.3 Tests for influence quantities of type S . 25
5.3 Point of test . 25
5.4 Statistical fluctuations . 25
5.5 Radiation sources . 26
5.6 Work place neutron fields. 26
5.7 Consideration of several detectors or signals in a dose rate meter . 26
5.8 Functionality test . 27
5.8.1 General . 27
5.8.2 Pre-test (preparation) . 27
5.8.3 Post-test . 27
6 Radiation detection requirements . 28
6.1 General . 28

IEC 61322:2019  IEC 2019 – 3 –
6.2 Consideration of the uncertainty of the conventional true value . 28
6.3 Linearity of dose rate response . 28
6.3.1 Requirements . 28
6.3.2 Tests to be performed . 28
6.3.3 Type tests . 28
6.3.4 Routine tests . 29
6.3.5 Test method using sources . 29
6.3.6 Interpretation of the results of the test using sources . 29
6.3.7 Test procedure with variation of the calibration distance . 29
6.3.8 Interpretation of the results of the test with variation of the calibration
distance . 29
6.3.9 Equivalent electrical test method . 30
6.3.10 Interpretation of the equivalent electrical test result . 30
6.4 Variation of the response due to neutron energy . 30
6.4.1 General . 30
6.4.2 Requirements . 30
6.4.3 Method of test. 31
6.4.4 Interpretation of the results . 32
6.5 Variation of response with angle of incidence. 32
6.5.1 General . 32
6.5.2 Requirements . 32
6.5.3 Method of test. 34
6.5.4 Interpretation of the results of the test . 35
6.6 Response to other external ionizing radiations . 35
6.6.1 Alpha and beta radiations . 35
6.6.2 Photon radiation . 35
6.7 Overload characteristics . 36
6.7.1 Requirements . 36
6.7.2 Method of test. 36
6.8 Statistical fluctuations . 37
6.8.1 Requirements . 37
6.8.2 Method of test. 37
6.8.3 Interpretation of the results . 37
6.9 Response time . 37
6.9.1 Requirements . 37
6.9.2 Method of test. 38
6.10 Zero drift . 38
6.10.1 Requirements . 38
6.10.2 Method of test. 38
6.11 Alarm requirements . 38
6.11.1 Requirements . 38
6.11.2 Method of test. 39
6.12 Equipment failure alarms . 39
6.12.1 Requirements . 39
6.12.2 Method of test. 39
6.13 False alarm test . 39
6.13.1 Requirements . 39
6.13.2 Method of test. 39
6.14 Alarm response time and stability . 39

– 4 – IEC 61322:2019  IEC 2019
6.14.1 Requirements . 39
6.14.2 Method of test. 39
6.15 Warm-up . 40
6.15.1 Requirements . 40
6.15.2 Method of test. 40
6.16 Power supplies . 41
6.16.1 Requirements . 41
6.16.2 Method of test. 41
7 Environmental requirements . 41
7.1 General . 41
7.2 Ambient temperature. 42
7.2.1 Requirements . 42
7.2.2 Method of test. 42
7.3 Relative humidity . 42
7.3.1 Requirements . 42
7.3.2 Method of test. 42
7.4 IP classification . 43
7.4.1 Requirements . 43
7.4.2 Method of test. 43
8 Mechanical requirements . 43
8.1 General . 43
8.2 Microphonics/impact . 43
8.2.1 Requirements . 43
8.2.2 Method of test. 43
9 Electromagnetic requirements . 44
9.1 General . 44
9.2 Emission of electromagnetic radiation . 45
9.2.1 Requirements . 45
9.2.2 Method of test. 45
9.3 Electrostatic discharge . 45
9.3.1 Requirements . 45
9.3.2 Method of test. 45
9.4 Radio frequency disturbance . 46
9.4.1 Requirements . 46
9.4.2 Method of test. 46
9.5 Magnetic fields . 46
9.5.1 Requirements . 46
9.5.2 Method of test. 46
9.6 Alternating current powered equipment requirements . 47
9.6.1 Voltage and frequency fluctuations . 47
9.6.2 Immunity from conducted RF . 47
9.6.3 Surges and ring waves . 48
10 Documentation . 48
10.1 Type test report . 48
10.2 Certificate . 48
10.3 Operation and maintenance manual . 49
Annex A (informative) Neutron fluence-to-ambient dose equivalent conversion
coefficients . 50

IEC 61322:2019  IEC 2019 – 5 –
Bibliography . 53

Figure 1 – Test for angular response . 33
Figure A.1 – Neutron fluence-to-ambient dose equivalent conversion coefficients for
mono-energetic neutrons [3] . 51

Table 1 – Reference and standard test conditions . 23
Table 2 – Radiation characteristics of ambient neutron dose equivalent rate meters . 24
Table 3 – Electrical and environmental characteristics of ambient dose equivalent rate

meters . 40
Table 4 – Maximum values of deviation due to electromagnetic disturbances. 44
Table 5 – Emission frequency range . 45
Table A.1 – Neutron fluence-to-ambient dose equivalent conversion coefficients for
mono-energetic neutrons ([1], [3], [4], [7]) . 50
Table A.2 – Neutron fluence-to-ambient dose equivalent conversion coefficients for the
neutron reference radiation sources ([3] and ISO 8529-3) . 52

– 6 – IEC 61322:2019  IEC 2019
INTERNATIONAL ELECTROTECHNICAL COMMISSION
____________
RADIATION PROTECTION INSTRUMENTATION –
INSTALLED AMBIENT DOSE EQUIVALENT RATE METERS,
WARNING AND MONITORING ASSEMBLIES FOR NEUTRONS
WITH ENERGIES FROM THERMAL TO 20 MeV

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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6) All users should ensure that they have the latest edition of this publication.
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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 61322 has been prepared by subcommittee 45B: Radiation
protection instrumentation, of IEC technical committee 45: Nuclear instrumentation.
This second edition cancels and replaces the first edition published in 1994. This edition
constitutes a technical revision.
This edition includes the following significant technical changes with respect to the previous
edition:
a) this document has been updated to take account of the requirements of the relevant IEC
standards, IEC 60532:2010 and IEC 61005:2014.

IEC 61322:2019  IEC 2019 – 7 –
The text of this document is based on the following documents:
FDIS Report on voting
45B/944/FDIS 45B/952/RVD
Full information on the voting for the approval of this document 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 61322:2019  IEC 2019
RADIATION PROTECTION INSTRUMENTATION –
INSTALLED AMBIENT DOSE EQUIVALENT RATE METERS,
WARNING AND MONITORING ASSEMBLIES FOR NEUTRONS
WITH ENERGIES FROM THERMAL TO 20 MeV

1 Scope
This document applies to installed dose equivalent rate meters, warning assemblies and
monitors, as defined below. It covers equipment intended to measure neutron radiation in
dose equivalent rates in the energy region between thermal and 20 MeV for the purposes of
radiation protection.
Assemblies of this type are commonly defined as area radiation monitors. They are normally
employed to determine continuously the radiological situation in working areas in which the
radiation field may change with time, for example, nuclear power plants, particle accelerators,
high-activity laboratories, fuel reprocessing plants, etc., and provide alarms when the
radiation field goes outside predetermined limits.
The assemblies considered in this document comprise at least:
– a detector assembly, which may, for example, consist of a detector probe (for thermal
3 6
neutrons such as BF proportional counter, He proportional counter, LiI(Tl) scintillation
detector, etc.) and a moderating and absorbing medium surrounding the detector;
– a processing assembly, which may be fitted into a centralized panel, which, in the case of
warning assemblies and monitors, provides signal outputs and contacts capable of
activating alarm or other trip circuits;
– alternatively, the case when all the processing electronics are placed within the detection
unit (so called "smart blocks") may be considered. In this case the functions of the
processing assembly will be composed of only the indication, the providing signal outputs
and contacts.
This document specifies general characteristics, general test procedures, radiation
characteristics, as well as electrical, mechanical, safety, and environmental characteristics, as
well as the identification certificate for the assemblies defined in the scope.
Assemblies designed to perform combined functions comply with the requirements pertaining
to each of these functions.
This document is not applicable to criticality monitors covered by IEC 60860, or to assemblies
intended to give information about operational parameters of nuclear plants for control
purposes. This document is not applicable to the operating characteristics of indicating or
recording instruments as such (for instance, indicating meters, recorders, etc.). The
characteristics of such instruments are in conformity with the general requirements
appropriate to them.
This document does not cover hand-held neutron dose (rate) meters and instruments that are
covered in IEC 61005.
No tests are specified in this document for performance requirements in pulsed radiation
fields. It is understood that an assembly designed to meet this document may not be suitable
for use in these fields.
IEC 61322:2019  IEC 2019 – 9 –
2 Normative references
The following documents are referred to in the text in such a way that some or all of their
content constitutes requirements 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 60050-395:2014, International Electrotechnical Vocabulary (IEV) – Part 395: Nuclear
instrumentation: Physical phenomena, basic concepts, instruments, systems, equipment and
detectors
IEC 60529:1989, Degrees of protection provided by enclosures – IP Code
IEC 61000-4-2:2008, Electromagnetic compatibility (EMC) – Part 4-2: Testing and measuring
techniques – Electrostatic discharge immunity test
IEC 61000-4-3:2006, Electromagnetic compatibility (EMC) – Part 4-3: Testing and measuring
techniques – Radiated, radio-frequency, electromagnetic field immunity test
IEC 61000-4-5:2014, Electromagnetic compatibility (EMC) – Part 4-5: Testing and measuring
techniques – Surge immunity test
IEC 61000-4-6:2013, Electromagnetic compatibility (EMC) – Part 4-6: Testing and measuring
techniques – Immunity to conducted disturbances induced by radio-frequency fields
IEC 61000-4-8, Electromagnetic compatibility (EMC) – Part 4-8: Testing and measuring
techniques – Power frequency magnetic field immunity test
IEC 61000-4-12, Electromagnetic compatibility (EMC) – Part 4-12: Testing and measuring
techniques – Ring wave immunity test
IEC 61187:1993, Electrical and electronic measuring equipment – Documentation
IEC 61508 (all parts), Functional safety of electrical/electronic/programmable electronic
safety-related systems
ISO 4037-1:2019, Radiological protection – X and gamma reference radiation for calibrating
dosemeters and doserate meters and for determining their response as a function of photon
energy – Part 1: Radiation characteristics and production methods
ISO 4037-2:2019, Radiological protection – X and gamma reference radiation for calibrating
dosemeters and doserate meters and for determining their response as a function of photon
energy – Part 2: Dosimetry for radiation protection over the energy ranges from 8 keV to 1,3
MeV and 4 MeV to 9 MeV
ISO 4037-3:2019, Radiological protection – X and gamma reference radiation for calibrating
dosemeters and doserate meters and for determining their response as a function of photon
energy – Part 3: Calibration of area and personal dosemeters and the measurement of their
response as a function of energy and angle of incidence
ISO 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

– 10 – IEC 61322:2019  IEC 2019
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
ISO 11929 (all parts): Determination of the characteristic limits (decision threshold, detection
limit and limits of the coverage 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
3 Terms and definitions, abbreviated terms 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.
ISO and IEC maintain terminological databases for use in standardization at the following
addresses:
• IEC Electropedia: available at http://www.electropedia.org/
• ISO Online browsing platform: available at http://www.iso.org/obp
NOTE For clarity and text conciseness in this document 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 document
it is understood that "neutron ambient dose equivalent rate meter" is meant.
3.1.1
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 .
3.1.2
neutron fluence rate
flux density

Φ
quotient of dΦ by dt, where dΦ is the increment of neutron fluence in the time interval dt:
d

Φ⋅
dt
−2 −1
Note 1 to entry: The unit of neutron fluence rate is m s .

IEC 61322:2019  IEC 2019 – 11 –
3.1.3
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
[1], [2], [3], [4]
the direction of the aligned field
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.
3.1.4
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
*
d1H 0
( )
*

H (10)=
dt
3.1.5
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.
3.1.6
calibration distance
distance between the reference point of the assembly and the centre of the calibration source
3.1.7
reference point of an assembly
physical or virtual mark or marks on the assembly to be used in order to position it at the test
point. This mark is usually either the geometric centre of the detector or its effective centre
Note 1 to entry: Effective reference point of an assembly is located at a distance, stated by a manufacturer for
specified energy, from a reference point of the assembly to be used in order to position the assembly at a point
where the conventional true value of a quantity to be measured is known.
3.1.8
conventional true value

H
t
quantity value attributed by agreement to a quantity for a given purpose
Note 1 to entry: In this document the quantity is the dose equivalent rate.
Note 2 to entry: Sometimes a conventional true value is an estimate of a true quantity value.
Note 3 to entry: A conventional true value is generally accepted as being associated with a suitably small
measurement uncertainty, which might be zero.
____________
Numbers in square brackets refer to the Bibliography.

– 12 – IEC 61322:2019  IEC 2019
3.1.9
indicated value

H
i
value given by the (digital) indication of the dose rate meter in unit of dose equivalent rate
3.1.10
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 3.1.11), and
Φ
h is the neutron fluence-to-dose conversion coefficient (see definition 3.1.5).
Φ
3.1.11
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 (doserate meter) for the neutron fluence, and
Φ is the conventional true value of the neutron fluence to which the instrument has been
exposed.
Note 1 to entry: The unit of neutron fluence response is m .
3.1.12
reference response
R
r
response for a reference value of the quantity to be measured under reference conditions

H
r
R =
r

H
t
where

H is the corresponding indicated value of the quantity to be measured under reference
r
conditions, and

H is the conventional true value (3.1.8) under reference conditions
t
Note 1 to entry: The reference response is the reciprocal of the reference calibration factor.
Note 2 to entry: The reference values for the dose rate are given in Table 1.

IEC 61322:2019  IEC 2019 – 13 –
3.1.13
relative response
r
quotient of the response R (3.1.11) and the reference response R (3.1.12)
r
R
r=
R
r
3.1.14
response of a radiation measuring assembly
R
ratio, under specified conditions, given by the relation

H
i
R=

H
t
where

H is the indicated value of the quantity (3.1.9) measured by the instrument under test,
i
and

H is the conventional true value of this quantity (3.1.8).
t
3.1.15
relative error of an indication
I
relative error, I, in the indication of an assembly is given as a percentage, by the relationship:

HH−
it
I(%) ×100

H
t
3.1.16
coefficient of variation
v

ratio of the experimental standard deviation s to the arithmetic mean H of a set of n

H
indications . It is given by the following formula:
j
n
s 11
 
v==⋅ ⋅ HH−
∑( j )
 n−1
HH
j=1
3.1.17
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 document
3.1.18
manufacturer
designer and seller of the equipment
3.1.19
purchaser
user (operator) of the equipment
=
– 14 – IEC 61322:2019  IEC 2019
3.1.20
order of magnitude
range of measurement or levels to be measured which differ by about a factor of ten for one
order of magnitude, one hundred for two, a thousand for three and so on
3.1.21
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
3.1.22
background level
radiation field in which the instrument is intended to operate, including that produced by
naturally occurring radioactive material and cosmic radiation
3.1.23
deviation
D
difference between the indicated values for the same value of the measurand of a dose
equivalent rate meter, when made under reference conditions and when subject to an
influence quantity

DH − H
ir
where

H is the indicated value under the effect of an influence quantity, and
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.
3.1.24
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.
3.1.25
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 en
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