IEC 62484:2010

IEC 62484 ®
Edition 1.0 2010-05
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
Radiation protection instrumentation –
Spectroscopy-based portal monitors used for the detection and identification of
illicit trafficking of radioactive material

Instrumentation pour la radioprotection –
Moniteurs spectroscopiques pour portiques d'accès utilisés pour la détection et
l'identification du trafic illicite des matières radioactives

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IEC 62484 ®
Edition 1.0 2010-05
INTERNATIONAL
STANDARD
NORME
INTERNATIONALE
Radiation protection instrumentation –
Spectroscopy-based portal monitors used for the detection and identification of
illicit trafficking of radioactive material

Instrumentation pour la radioprotection –
Moniteurs spectroscopiques pour portiques d'accès utilisés pour la détection et
l'identification du trafic illicite des matières radioactives

INTERNATIONAL
ELECTROTECHNICAL
COMMISSION
COMMISSION
ELECTROTECHNIQUE
PRICE CODE
INTERNATIONALE
W
CODE PRIX
ICS 13.280 ISBN 978-2-88910-914-2
– 2 – 62484 © IEC:2010
CONTENTS
FOREWORD.5
1 Scope and object.7
2 Normative references .7
3 Terms and definitions, abbreviations, quantities and units .8
3.1 Terms and definitions .8
3.2 Abbreviations .10
3.3 Quantities and units .11
4 Design requirements .12
4.1 General requirements.12
4.1.1 Pedestrian monitor .12
4.1.2 Vehicle monitor.13
4.1.3 Rail vehicle monitor (includes rail transported containers) .13
4.1.4 Package (or conveyor) monitor .13
4.2 Physical configuration .14
4.3 Spectral identification and count rate information .14
4.4 Indication features.15
4.5 Occupancy and speed sensors for vehicle monitors .15
4.6 Markings .15
4.7 Power supply.15
4.7.1 Requirements .15
4.7.2 Method of test .16
4.8 Protection of switches .16
4.9 Energy and count rate range .16
4.10 Communications protocol and data format.16
4.11 User interface.16
4.11.1 Guidance regarding alarm logic .16
4.11.2 Audible (sound) alarm .17
4.11.3 Visual indicators .17
4.11.4 Warning indicators.17
4.11.5 Basic indications and functions.17
4.11.6 Advanced indications and functions .18
5 Radiation detection and indication performance requirements .18
5.1 General test conditions.18
5.1.1 Nature of tests.18
5.1.2 Reference conditions and standard test conditions .18
5.1.3 Statistical fluctuations.18
5.2 Reference radiation .19
5.3 Alarm categorization.19
5.4 False alarms .19
5.4.1 Requirements .19
5.4.2 Method of test .19
5.5 Response to gamma radiation .19
5.5.1 Requirements .19
5.5.2 Method of test .19
5.6 Radiation intensity and identification alarm.20
5.6.1 Requirements .20

62484 © IEC:2010 – 3 –
5.6.2 Method of test .20
5.7 Response to neutron radiation.20
5.7.1 Requirements .20
5.7.2 Method of test .20
5.8 Over-range.20
5.8.1 Requirements .20
5.8.2 Method of test .21
5.9 Neutron indication in the presence of photons .21
5.9.1 Requirements .21
5.9.2 Method of test .21
5.10 Background effects.21
5.10.1 Requirements .21
5.10.2 Method of test .21
5.11 Radionuclide identification.22
5.11.1 Radionuclide categorization.22
5.11.2 Radionuclide identification qualification .22
5.11.3 General requirements for testing radionuclide identification ability.22
5.11.4 Single radionuclide identification .23
5.11.5 Identification of shielded radionuclides .24
5.11.6 Simultaneous radionuclide identification and masking.25
5.11.7 Over-range characteristics for identification.26
5.11.8 Pile-up effects .26
5.11.9 Radionuclide not in library .27
5.12 Environmental tests.27
5.12.1 Ambient temperature .27
5.12.2 Humidity tests.28
5.12.3 Dust and moisture resistance tests .28
5.13 Mechanical requirements.29
5.13.1 Vibration.29
5.13.2 Microphonics/Impact.30
5.14 Electromagnetic performance requirements.30
5.14.1 Electrostatic discharge (ESD) .30
5.14.2 Radio frequency .30
5.14.3 Radiated RF emissions .31
5.14.4 Conducted disturbances .31
5.14.5 Magnetic fields .31
5.14.6 Surges and oscillatory waves .32
6 Documentation .32
6.1 Type test report.32
6.2 Certificate .32
6.3 Operation and maintenance manuals.32
Annex A (informative) Identification of uranium isotopes .36
Bibliography.37

Figure 1 – Diagram of mounting dimensions for radionuclide identifying portal monitors .9

Table 1 – Speed of moving sources .33
Table 2 – Evaluation distances for different applications .33

– 4 – 62484 © IEC:2010
Table 3 – Reference and standard test conditions.34
Table 4 – Approximate activity values for gamma-ray and neutron sources.34
Table 5 – Example of alarm categorizations.35
Table 6 – Emission limits .35
Table A.1 – Uranium detection and identification guidance .36

62484 © IEC:2010 – 5 –
INTERNATIONAL ELECTROTECHNICAL COMMISSION
____________
RADIATION PROTECTION INSTRUMENTATION –
SPECTROSCOPY-BASED PORTAL MONITORS USED
FOR THE DETECTION AND IDENTIFICATION OF ILLICIT
TRAFFICKING OF RADIOACTIVE MATERIAL

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.
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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
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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
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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 IEC 62484 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/634/FDIS 45B/644/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 – 62484 © IEC:2010
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.
62484 © IEC:2010 – 7 –
RADIATION PROTECTION INSTRUMENTATION –
SPECTROSCOPY-BASED PORTAL MONITORS USED
FOR THE DETECTION AND IDENTIFICATION OF ILLICIT
TRAFFICKING OF RADIOACTIVE MATERIAL

1 Scope and object
This International Standard specifies the operational and performance requirements for
spectroscopy-based portal monitors used for the detection and identification of illicit trafficking
of radioactive material. Spectroscopy-based portal monitors have the ability to detect gamma
and neutron radiation and identify gamma-emitting radionuclides that may be present in or on
persons, vehicles, containers, or packages in a static or transient mode of operation.
Operational requirements established by this standard include radiation detection and
gamma-emitting radionuclide identification, and those requirements associated with the
expected electrical, mechanical, and environmental conditions when a portal monitor is
deployed.
The object of this standard is to establish performance requirements and to give examples of
acceptable test methods, and to specify general characteristics, general test conditions,
radiation characteristics, electrical safety, and environmental characteristics to determine if a
portal monitor meets the requirements of this standard.
Special applications, which may include a monitor’s operation under weather conditions or for
detection needs not addressed by this standard, shall require additional testing.
Obtaining operating performance that meets or exceeds the specifications as stated in this
standard depends upon properly installing the monitor, establishing appropriate operating
parameters, providing security for the monitor, maintaining calibration, implementing a
suitable response testing and maintenance program, auditing compliance with quality
requirements, and providing proper training for operating personnel.
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 60050-393:2003, International Electrotechnical Vocabulary (IEV) – Part 393: Nuclear
instrumentation – Physical phenomena and basic concepts
IEC 60050-394:2007, International Electrotechnical Vocabulary (IEV) – Part 394: Nuclear
instrumentation – Instruments, systems, equipment and detectors
IEC 60529:1989, Degrees of protection provided by enclosures (IP Code)
Amendment 1 (1999)
IEC 61000-4-2:2008, Electromagnetic compatibility (EMC) – Part 4-2: Testing and measure-
ment techniques – Electrostatic discharge immunity test
IEC 61000-4-3:2006, Electromagnetic compatibility (EMC) – Part 4-3: Testing and measure-
ment techniques – Radiated, radio-frequency, electromagnetic field immunity test

– 8 – 62484 © IEC:2010
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
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 from 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 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 neutron energy and angle of
incidence
th
International Bureau of Weights and Measures: The International System of Units, 8 edition,
3 Terms and definitions, abbreviations, 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 60050-393 and IEC 60050-394 apply.
3.1.1
acceptable (or correct) identification
when a monitor identifies the radionuclide(s) that are present
3.1.2
alarm
an audible, visual, or other signal activated when the instrument reading exceeds a preset
value, falls outside of a preset range, or when the instrument detects and/or identifies the
presence of the source of radiation according to a preset condition
[IEV 393-18-03, modified]
3.1.3
alarm criteria
conditions that cause a monitor to alarm
3.1.4
confidence indication
an indication provided by the monitor on the reliability assigned to the determined
identification
62484 © IEC:2010 – 9 –
3.1.5
detection zone
volume where radiation emitted by an object or person may be detected by the detection
assembly(s). For two-sided monitors, the detection zone is located between opposing
detection assemblies; for single-sided monitors, the detection zone is adjacent to the
detection assembly surface (see Figure 1)
3.1.6
evaluation distances
the distance between an evaluation test source and the exterior surface of the detection
assembly(s) that faces the detection zone (see Figure 1)

Evaluation
distance
D/2
Evaluation
D D
distance
IEC  839/10
Key
D  Distance between detection assemblies or evaluation distance for single-sided monitors
(D = 5 m for single-sided vehicle monitors and 1 m for single-sided pedestrian or package monitors. For fixed
monitors, “D” is stated by the manufacturer.)
Figure 1 – Diagram of mounting dimensions for radionuclide
identifying portal monitors
3.1.7
false alarm
alarm not caused by an increase in radiation level over background conditions
[IEC 62401]
3.1.8
false identification
misinterpretation of data being measured by a system leading to the incorrect identification of
radionuclide(s) or isotopes of all radionuclides that are present
3.1.9
innocent alarm
an alarm, as designated by the operator, caused by an increase in radiation from radioactive
material such as NORM (e.g., fertilizer, tiles, ceramics), legal radioactive shipments, or in-vivo
medical radionuclides
3.1.10
live time
time interval during which a detection assembly is sensitive to the input signal
Detection zone
Detection zone
Detection zone
– 10 – 62484 © IEC:2010
[IEV 394-39-31, modified]
3.1.11
manufacturer
includes the designer of the equipment
3.1.12
occupancy
when the detection zone is occupied with an object (e.g., person, vehicle, package) that is
being monitored
3.1.13
peripheral device
any device connected to the system other than the detector or detection assembly that is not
required for operation
3.1.14
purchaser
includes the user of the equipment
3.1.15
radioactive material
in this standard, radioactive material includes special nuclear material and any radioactive
source, unless otherwise specifically noted
3.1.16
reference point of the detection zone
the point at the geometric centre of the detection zone for two-sided monitors or at the
geometric centre of the detection zone that is adjacent to a single-sided monitor at a distance
from the detection assembly surface that is based on the monitor type (Figure 1)
3.1.17
run time
the duration (i.e., elapsed clock time) of the acquisition of the spectrum or other data
3.1.18
standard test sources
a set of radioactive sources required to perform an evaluation that are traceable to a national
or international standard
3.1.19
static mode
when the object being monitored is stationary within the detection zone for the monitoring
period
3.1.20
transient mode
when the object being monitored passes through the detection zone
3.2 Abbreviations
3.2.1
ESD
electrostatic discharge
3.2.2
DU
depleted uranium
62484 © IEC:2010 – 11 –
3.2.3
HEU
highly enriched uranium
3.2.4
IAEA
International Atomic Energy Agency
3.2.5
LEU
low enriched uranium
3.2.6
NORM
naturally occurring radioactive material
3.2.7
PMMA
polymethyl methacrylate
3.2.8
RF
radio frequency
3.2.9
RGPu
reactor grade plutonium
3.2.10
RH
relative humidity
3.2.11
SNM
special nuclear material
3.2.12
WGPu
weapons grade plutonium
3.3 Quantities and units
. The definitions of
In the present standard, units of the International System (SI) are used
radiation quantities are given in IEC 60050-393 and IEC 60050-394. The corresponding old
units (non SI) are indicated in brackets.
Nevertheless, the following units may also be used:
–19
– for energy: electron-volt (symbol: eV), 1 eV = 1,602 × 10 J;
– for magnetic flux density: gauss (G);
– for time: years (symbol: y), days (symbol: d), hours (symbol: h), minutes (symbol: min).
Multiples and submultiples of SI units will be used, when practicable, according to the SI
system.
—————————
th
International Bureau of Weights and Measures: The International System of Units, 8 edition, 2006.

– 12 – 62484 © IEC:2010
4 Design requirements
4.1 General requirements
The equipment addressed by this standard shall detect the presence of gamma-ray and
neutron sources, and identify gamma-emitting radionuclide(s) in objects, containers, vehicles,
or in, or being carried by, pedestrians.
An alarm shall be activated when the signal from the detection system exceeds an alarm or
preset condition (user selectable for radiation level or identification result). Measurement
occurs when the object passes through the detection zone or with the object static within the
detection zone where the user performs controlled analyses of the object (i.e., enters
collection time and/or activates the count).
Passage speeds for transient mode testing are stated in Table 1. Testing at different speeds
may be performed as a special test upon agreement between the manufacturer and user. The
manufacturer shall state the time required for static measurements.
Monitors shall be capable of operating independently of any peripheral device or remote
station and shall be unaffected by any malfunction of a peripheral device.
According to their use, spectroscopy-based portal monitors are classified as:
– pedestrian monitor,
– vehicle (including containerized cargo handlers) monitor,
– rail vehicle monitor, and
– package monitor (i.e., conveyor).
The detection zone is the area located adjacent to a single-sided detection assembly or
between two or more detection assemblies where the measurement of radiation takes place
(Figure 1). The size of the detection zone is based on the classification of use. If a monitor is
used in two or more classifications, its detection zone shall be appropriate for each
classification. The detection zone shall be of a size that ensures that all objects which could
move through the detection zone are monitored. The manufacturer shall state the size of the
detection zone for which the requirements stated in this standard are met.
The monitor shall meet the performance requirements of this standard when installed as
tested. Operational conditions such as separation distance (distance between opposing
detection assemblies) and background radiation shall be considered when installing the
monitor. The manufacturer shall state the distance and background level at which the monitor
meets this standard. If the manufacturer-stated distance is different from that required by this
standard, testing should be carried out at the manufacturer stated distance.
It is important to be able to identify the person or vehicle that caused an alarm. The alarm
should be generated within a period of time to ensure that the object that caused an alarm
can be identified. This is important if complex algorithms are in place that need a finite
process time. It becomes more important if a constant stream of traffic is being monitored
(i.e., pedestrians).
4.1.1 Pedestrian monitor
Pedestrian monitors shall provide a detection zone to ensure that people are monitored. For
evaluation purposes, the height of the detection zone shall be 1,9 m measured from 0,1 m
above the ground. The recommended distance between detection assemblies for evaluation
purposes is listed in Table 2 or provided by the manufacturer for monitors where each
detection assembly is part of a structure with a fixed distance between each assembly.

62484 © IEC:2010 – 13 –
Pedestrian monitors may use a single detection assembly (single-sided) or multiple opposing
detection assemblies with or without detectors across the top and/or bottom part of the
detection zone. For monitors with a restricted passage height, the height of the detection zone
shall be from the ground or base surface to the top surface of the monitors’ detection
assembly.
The passage speed for transient mode testing shall be the speed listed in Table 1.
4.1.2 Vehicle monitor
Vehicle monitors shall provide a detection zone that ensures that the entire vehicle is
monitored during passage when operated in transient mode. The height of the detection zone
shall be stated by the manufacturer.
NOTE Different heights may be used based on the region of use and associated local requirements.
For trucks, the height of the detection zone for testing purposes shall be 4,3 m measured from
0,2 m above the ground. For passenger cars, the height of the detection zone for testing
purposes shall be 2,8 m measured from 0,2 m above the ground. The distance between
vertical detection assemblies for evaluation purposes is listed in Table 2 or is given by the
manufacturer.
Passage speeds for transient mode testing are stated in Table 1. Testing at slower speeds
may be performed as a special test upon agreement between the manufacturer and user. The
manufacturer shall state the time required for static measurements.
4.1.3 Rail vehicle monitor (includes rail transported containers)
Rail vehicle monitors shall provide a detection zone that ensures that the entire rail vehicle is
monitored during passage. For evaluation purposes, the height of the detection zone shall be
5,7 m measured from 0,3 m above the rail (for test purposes, the ground surface should be
considered as the top of the rail). For monitors with a restricted passage height, the top of the
detection zone shall be to the top surface of the monitors’ detection assembly. The distance
between vertical detection assemblies for evaluation purposes is listed in Table 2 or is given
by the manufactured dimension.
NOTE Different heights may be used based on the region of use and associated local requirements.
The passage speed for transient mode testing shall be the speed listed in Table 1.
4.1.4 Package (or conveyor) monitor
Package or conveyor monitors shall provide a detection zone that ensures that items moving
through the detection zone are monitored. The dimensions of the detection zone shall be
stated by the manufacturer. Monitors may use a single detection assembly (single-sided) or
multiple opposing detection assemblies which may have detectors across the top and/or
bottom part of the detection assembly (multi-sided).
For evaluation purposes, the height of the detection zone shall be
a) 1 m from the base surface (that surface which corresponds to the ground or conveyor
bottom surface) for detectors mounted below the base surface, or
b) 1 m from the base surface to the face of the detection assembly for detectors mounted
above the base surface. For monitors with a restricted passage height, the height of the
detection zone shall be from the base surface to the manufacturer-specified distance.
The passage speed for transient mode testing shall be the speed listed in Table 1.

– 14 – 62484 © IEC:2010
4.2 Physical configuration
The monitor may consist of one or several detector assemblies and a data processing unit.
Enclosure(s) provided for outdoor assemblies should be designed to meet the IP54
designation as stated in IEC 60529.
The detection assemblies for road and rail vehicle monitoring may be subjected to vibration.
Monitors and installation techniques (i.e., concrete pads, support brackets) shall be designed
to prevent normal vibrations and shocks from interfering with the operation of the detection
system.
Controls and adjustments that may affect the operation of the monitor including calibration
and alarm settings shall be designed so that access to them is limited to authorized persons.
Provisions shall be made to permit testing of visual and/or sound warning indicators without
the use of radiation sources.
No additional radiation shielding shall be used to reduce ambient radiation levels when
evaluating monitors.
4.3 Spectral identification and count rate information
A displayed gamma-ray spectrum is not required during routine operation. The spectrum
display shall be available through manufacturer-defined user actions.
The monitor shall have the ability to internally store 100 alarm data sets using a method that
will prevent data loss in the event of loss of power. Each alarm data set shall contain
collection and identification results information including:
– Unprocessed spectrum (spectra for multi-detector systems)
– Time and date
– Run time and live time
– Identified radionuclides and categories
– Occupancy time (when occupancy sensors are used, or the data collection time when
occupancy sensors are not used)
– Transient speed (if applicable)
– Monitor identification
– Alarm condition (gamma-ray and/or neutron)
– Background (gamma-ray and neutron count rate, and spectrum)
– Gamma-ray count rate during measurement
– Neutron count rate during measurement
– Video record or image (e.g., photo, license plate/vehicle registration number), if available.
The monitor shall have the ability to internally store at least 3 h of measurement data or 1 000
complete occupancy data sets using a method that will prevent data loss in the event of loss
of power.
The monitor shall have the ability to transfer stored information including spectra at user
selectable intervals to an external device such as a computer.
The monitor shall have the ability to display gamma-ray and neutron count rate time-history
data internally or on an external device.

62484 © IEC:2010 – 15 –
An indication shall be displayed or otherwise provided (i.e., “not identified”, “unknown”) if a
radionuclide cannot be identified during or after a measurement takes place that activated an
alarm.
If a confidence indication is associated with the identification of a radionuclide(s), the
confidence value shall be provided in the data set and the manufacturer shall describe the
meaning of the displayed confidence value.
The monitor shall have the ability to perform identification measurements with an object static
in the detection zone. This selection of static or transient mode shall be user selectable. The
recommended measurement time for static mode shall stated by the manufacturer and be
user selectable. The maximum selectable measurement time shall be by agreement between
the manufacturer and user.
4.4 Indication features
The monitor shall provide an indication of its operational status and alarm condition, and be
capable of transmitting these signals to remote stations. The user shall have the ability to
select the visibility of the status indication.
All alarm indicators shall automatically or manually reset as defined by the user. Radiation
alarm function shall be user selectable based on count rate, radionuclide identification, and/or
radionuclide categorization.
4.5 Occupancy and speed sensors for vehicle monitors
Occupancy and speed sensors:
– shall be able to detect presence and to estimate vehicle speed, indicate if a vehicle stops
within the detection zone, and not count a single vehicle or object in the detection zone
more than once;
– should be capable of operating on a mix of traffic as applicable to the expected use (e.g.,
cars, vans, pickup trucks, buses, cargo trucks, trains), and
– should function under all environmental conditions stated in this standard.
Rail monitors should have the ability to indicate the approximate location within the train that
caused an alarm when monitoring multi-car trains.
For test purposes, a system that uses sensors to activate a measurement should have the
capability to perform a user-selected number of consecutive discrete measurements
automatically without the need to activate the sensor. Function variables such as occupancy
time and time between occupancies shall be selectable by the user.
4.6 Markings
Internal controls shall be identified through markings on electrical circuit boards and/or
individual components, and identification in technical manuals.
Markings shall be permanently fixed under normal conditions of use.
Exterior markings shall be limited to the manufacturer’s unique serial number, and voltage
and current requirements.
4.7 Power supply
4.7.1 Requirements
Mains operated assemblies should be designed to operate from single-phase AC supply
voltage of 100 V to 240 V and from 47 Hz to 63 Hz.

– 16 – 62484 © IEC:2010
If backup power is provided, the manufacturer shall state the expected operating time and
conditions in which the time was determined.
4.7.2 Method of test
137 252
Place the Cs and Cf test sources in a location that provides stable readings (minimal
fluctuations so that any real changes caused by voltage or frequency changes are
observable). With the supply voltage at its nominal value determine the average gamma-ray
and neutron readings from a sufficient series of readings and perform a 10 trial radionuclide
identification of Cs. Record the identification results.
Increase the supply voltage to 12 % above the nominal value. Determine and record the
gamma-ray and neutron average readings and perform a 10 trial radionuclide identification
using Cs. Decrease the supply voltage to 12 % below the nominal value and again
determine and record the average readings, and perform a 10-trial radionuclide identification.
The above tests shall be repeated but instead of changing the voltage, the frequency shall be
changed from 58 Hz to 63 Hz for 60 Hz supply voltage or 47 Hz to 53 Hz for 50 Hz supply
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