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13.280 - Radiation protection

ICS 13.280 Details

Radiation protection

Strahlenschutz

Protection contre les rayonnements

Varstvo pred sevanjem

General Information

Parent
13 - ENVIRONMENT. HEALTH PROTECTION. SAFETY

Frequently Asked Questions

ICS 13.280 is a classification code in the International Classification for Standards (ICS) system. It covers "Radiation protection". The ICS is a hierarchical classification system used to organize international, regional, and national standards, facilitating the search and identification of standards across different fields.

There are 773 standards classified under ICS 13.280 (Radiation protection). These standards are published by international and regional standardization bodies including ISO, IEC, CEN, CENELEC, and ETSI.

The International Classification for Standards (ICS) is a hierarchical classification system maintained by ISO to organize standards and related documents. It uses a three-level structure with field (2 digits), group (3 digits), and sub-group (2 digits) codes. The ICS helps users find standards by subject area and enables statistical analysis of standards development activities.

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SIST
SIST EN ISO 8690:2026(Main)
Measurement of radioactivity - Gamma ray and beta emitting radionuclides - Test method to assess the ease of decontamination of surface materials (ISO 8690:2024)
EN ISO 8690:2026

This document applies to the testing of surfaces that may become contaminated by radioactive materials.
The ease of decontamination is a property of a surface and an important criterion for selecting surface
materials used in the nuclear industry, interim storage or disposal facilities from which contamination can
be removed easily and rapidly without damaging the surface. The test described in this document is a rapid
laboratory-based method to compare the ease of decontamination of different surface materials.
The results from the test can be one parameter to take into account when selecting surface coatings such
as varnish or impervious layers such as ceramics and other surfaces. The radionuclides used in this test
are those commonly found in the nuclear industry (137Cs, 134Cs and 60Co) in aqueous form. The test can also be adopted for use with other radionuclides and other chemical forms, depending on the customer requirements, if the solutions are chemically stable and do not corrode the test specimen.
The test does not measure the ease of decontamination of the surface materials in practical use, as this
depends on the radionuclide(s) present, their chemical form, the duration of exposure to the contaminant
and the environmental conditions amongst other factors.
The test method is not intended to describe general decontamination procedures or to assess the efficiency of decontamination procedures (see ISO 7503-1 to ISO 7503-3).
The test method is not suitable for use of radiochemicals if the radionuclide emits low energy gamma rays or beta particles that are readily attenuated in the surface.

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ISO
ISO 20785-4:2026(Main)
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 4: Validation of codes

This document is intended for the validation of codes used for the calculation of doses received by individuals on board aircraft. It gives guidance to radiation protection authorities and code developers on the basic functional requirements which the code fulfils. Depending on any formal approval by a radiation protection authority, additional requirements concerning the software testing can apply.

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ISO
ISO 12749-5:2026(Main)
Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 5: Nuclear reactors

This document encompasses the collection of terms, definitions, notes to entry and examples corresponding to nuclear reactors, excluding quantitative data. It provides the minimum essential information for each nuclear reactor concept represented by a single term. Full understanding of concepts requires background knowledge of the nuclear field. It is intended to facilitate communication and promote common understanding. The scope of this document does not cover nuclear fusion reactors. NOTE See Annex A for the methodology used to develop the vocabulary.

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CEN
EN ISO 8690:2026(Main)
Measurement of radioactivity - Gamma ray and beta emitting radionuclides - Test method to assess the ease of decontamination of surface materials (ISO 8690:2024)
SIST EN ISO 8690:2026

This document applies to the testing of surfaces that may become contaminated by radioactive materials.
The ease of decontamination is a property of a surface and an important criterion for selecting surface
materials used in the nuclear industry, interim storage or disposal facilities from which contamination can
be removed easily and rapidly without damaging the surface. The test described in this document is a rapid
laboratory-based method to compare the ease of decontamination of different surface materials.
The results from the test can be one parameter to take into account when selecting surface coatings such
as varnish or impervious layers such as ceramics and other surfaces. The radionuclides used in this test
are those commonly found in the nuclear industry (137Cs, 134Cs and 60Co) in aqueous form. The test can also be adopted for use with other radionuclides and other chemical forms, depending on the customer requirements, if the solutions are chemically stable and do not corrode the test specimen.
The test does not measure the ease of decontamination of the surface materials in practical use, as this
depends on the radionuclide(s) present, their chemical form, the duration of exposure to the contaminant
and the environmental conditions amongst other factors.
The test method is not intended to describe general decontamination procedures or to assess the efficiency of decontamination procedures (see ISO 7503-1 to ISO 7503-3).
The test method is not suitable for use of radiochemicals if the radionuclide emits low energy gamma rays or beta particles that are readily attenuated in the surface.

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IEC
IEC TR 62669:2026(Main)
Case studies supporting IEC 62232 - Determination of RF field strength, power density and SAR in the vicinity of radiocommunication base stations for the purpose of evaluating human exposure

IEC TR 62669:2026 presents a series of case studies in which electromagnetic field (EMF) exposure is evaluated in accordance with IEC 62232:2025 [1]. The case studies presented in this document involve intentionally radiating base stations (BSs). The BS transmits on one or more antennas using one or more frequencies in the range 110 MHz to 300 GHz. RF exposure assessments consider, as a minimum, the contribution of ambient sources in at least the 100 kHz to 300 GHz frequency range.
Case studies presented in this document illustrate typical usage of IEC 62232:2025 for the RF exposure assessments of the most common BS types, deployed in mobile and wireless networks, such as small cells, street cells, macro BSs, and parabolic dish antennas used for wireless transmission or mobile backhaul. Many case studies also illustrate the implementation of the actual maximum approach and RF exposure assessment of massive multiple-input, multiple-output (mMIMO) BSs, which are deployed in operational mobile networks, such as 5G.
The case studies are provided for guidance only and are not a substitute for a thorough understanding of the requirements of IEC 62232:2025. Based on the technical outcome and lessons learned from each case study, suggestions are made about RF assessment topics to be considered in the next edition of IEC 62232. New assessment techniques for metrics specified in ICNIRP-2020 [2], such as whole-body average SAR (wbSAR) above 10 GHz and absorbed power density (APD), are also introduced.
NOTE 1 Trade names and trademarks of measurement equipment and computation tools given in this document and in the attached test reports are examples of suitable products available commercially. This information is given for the convenience of users of this document and does not constitute an endorsement by IEC of these products.
NOTE 2 The lower frequency considered for ambient sources, 100 kHz, is derived from ICNIRP-2020 [2] and ICNIRP-1998 [3]. Some applicable exposure limit guidelines, however, require ambient fields to be evaluated as low as 3 kHz, e.g. IEEE Std C95.1-2019 [4] and Safety Code 6 [5].
This third edition cancels and replaces the second edition published in 2019. This edition constitutes a technical revision.
This edition includes the following significant technical changes with respect to the previous edition:
a) additional case studies and technical updates illustrating the implementation of IEC 62232:2025;
b) general implementation of the actual maximum approach for beamforming antennas;
c) validation of power or EIRP control features;
d) in-situ measurement and implementation of extrapolation methods;
e) introduction of emerging laboratory measurement methods for product compliance assessments.

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IEC
IEC TS 62461:2026(Main)
Radiation protection instrumentation - Determination of uncertainty in measurement

IEC TS 62461:2026 gives guidelines for the application of the uncertainty analysis accord­ing to ISO/IEC Guide 98‑3:2008 (GUM describing an analytical method for the uncertainty determination) and its Supplement 1:2008 (GUM S1 describing a Monte Carlo method for the uncertainty determination) for measurements of ionizing radiation. It does not include the uncertainty associated with the concept of the measuring quantity, e.g., the difference between Hp(10) on the ISO water slab phantom and on the person.
This document explains the principles of ISO/IEC Guide 98‑3:2008, its Supplement 1:2008 and the special considerations necessary for radiation protection at an example taken from individual dosimetry of external radiation.
This document is intended to assist the understanding of ISO/IEC Guide 98‑3:2008, ISO/IEC Guide 98‑3-SP1:2008 and other papers on uncertainty analysis. It cannot replace these papers, nor can it provide the background and justification of the arguments leading to the concept of ISO/IEC Guide 98‑3:2008 and ISO/IEC Guide 98‑3-SP1:2008.
Finally, this document gives a very simple method to judge whether a measured result is significantly different from zero or not based on ISO 11929.
This first edition of IEC TS 62461 cancels and replaces the second edition of IEC TR 62461 published in 2015. This edition includes the following significant technical changes with respect to the previous edition:
- several minor corrections;
- the addition of an example of the determination of the decision threshold and detection limit in accordance with ISO 11929.

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ISO
ISO 24953:2026(Main)
Textiles — Determination of iodine isotope adsorption efficiency of activated carbon fibre

This document specifies a method of testing the adsorption efficiency of activated carbon fibres, such as nonwoven fabric or fibrous felt with a thickness of less than 20 mm for adsorption and removal of iodine isotopes (I131), included in air or gas flow (exhaust).

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IEC
IEC 61526:2024/AMD1:2026(Amendment)
Amendment 1 - Radiation protection instrumentation - Measurement of personal dose equivalents for X, gamma, neutron and beta radiations - Active personal dosemeters
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IEC
IEC 61526:2024(Main)
Radiation protection instrumentation - Measurement of personal dose equivalents for X, gamma, neutron and beta radiations - Active personal dosemeters

IEC 61526:2024 applies to personal dosemeters with the following characteristics:
a) They are worn on the trunk, close to the eye, or on the extremities.
b) They measure the personal dose equivalents Hp(10), Hp(3), and Hp(0,07), from external X and gamma, neutron (not for Hp(3)), and beta radiations, and may measure the respective personal dose equivalent rates for the same radiations (for alarming purposes).
c) They have a digital indication. This indication may or may not be attached.
d) They have alarm functions for the personal dose equivalents or personal dose equivalent rates except for hybrid dosemeters. For hybrid dosemeters an alarm function for the personal dose equivalents shall be implemented in the associated readout system.
This document specifies requirements for the dosemeter and, if supplied, for its associated readout system.
This document specifies, for the dosemeters described above, general characteristics, general test procedures, radiation characteristics as well as electrical, mechanical, safety and envi­ronmental characteristics.
This edition includes the following significant technical changes with respect to the previous edition:
a) Modification of the title;
b) Inclusion of the measurement quantity for the dose in the lens of the eye, Hp(3);
c) Inclusion of measurement quantity for dose in the skin and extremities, Hp(0,07);
d) Inclusion of dosemeters between active and passive: "hybrid dosemeters";
e) Inclusion of software requirements;
f) Harmonization of requirements for linearity to IEC 62387;
g) Revised neutron energy response requirements.

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    166 pages
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SIST
SIST EN ISO 18090-1:2026(Main)
Radiological protection - Characteristics of reference pulsed radiation - Part 1: Photon radiation (ISO 18090-1:2026)
EN ISO 18090-1:2026

This document is directly applicable to pulsed X-radiation with pulse duration of 0,1 ms up to 10 s. This range covers the whole range used in medical diagnostics at the time of publication. Some specifications can also be applicable for much shorter pulses; one example is the air kerma of one pulse. Such a pulse can be produced, e.g. by X-ray flash units or high-intensity femtosecond-lasers. Other specifications are not applicable for much shorter pulses; one example is the time-dependent behaviour of the air kerma rate. This cannot be measurable for technical reasons as no suitable instrument is available, e.g. for pulses produced by a femtosecond-laser.
This document specifies the characteristics of reference pulsed radiation for calibrating and testing radiation protection dosemeters and dose rate meters with respect to their response to pulsed radiation. At this point, it is only concerned with the characteristics of single pulses. Single pulses are the most difficult for dosemeters to measure. Determining the dose for repeated pulses is easier, but still more difficult than for continuous radiation, i.e. the performance of the dosemeters when measuring repeated pulses lies between these extremes. The radiation characteristics includes the following:
time-dependent behaviour of the air kerma rate of the pulse;
time-dependent behaviour of the X-ray tube high voltage during the pulse;
uniformity of the air kerma rate within a cross-sectional area of the radiation beam;
air kerma of one radiation pulse;
air kerma rate of the radiation pulse;
repetition frequency.
This document does not define new radiation qualities but uses those radiation qualities specified in existing ISO and IEC standards. Instead, this document gives the link between the parameters for pulsed radiation and the parameters for continuous radiation specifying the radiation qualities. It does not specify specific values or series of values for the pulsed radiation field but specifies only those limits for the relevant pulsed radiation parameters that are required for calibrating dosemeters and dose rate meters and for determining their response depending on the said parameters.
The pulse parameters with respect to the phantom-related quantities were determined using conversion coefficients according to ISO 4037 (all parts). This is possible as the radiation qualities specified in existing ISO and IEC standards are used.
A given reference pulsed X-ray facility is characterized by the parameter ranges over which the full specifications and requirements according to this document are met. Therefore, not all reference pulsed X-ray facilities can produce pulses covering the same parameter ranges.

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IEC
IEC 63589-1:2026(Main)
Linear accelerator - Electron linear accelerator for radiation processing - Part 1: General requirements and test methods

IEC 63589-1:2026 specifies the general requirements and test methods of radiation processing electron linear accelerator device. The rules of naming, technical requirements, test methods, inspection rules, marking, packaging, storage, and transportation requirements are also provided.
This document applies to the electron linear accelerators for radiation processing with energy 1,0 MeV to 15 MeV.

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ISO
ISO 16659-2:2026(Main)
Ventilation systems for nuclear facilities — In-situ efficiency test methods for iodine traps with solid sorbent — Part 2: Radioactive CH3I method

This document specifies a test method using radioactive methyl iodide (CH3131I) as a tracer to determine the in-situ decontamination factor of an iodine trap. An in-situ test allows to reach the global efficiency of the trap characterized by the sorbent efficiency but also by the implementation of the trap within the ventilation duct) while the intrinsic efficiency of a charcoal is characterized in a laboratory by ISO 18417[9] (or other national standards such as ASTM D3803[10]). This document provides general and common requirements for this method to assess the efficiency of an iodine trap, but also, the tools requirements, accuracy and the provisions needed to ensure safety of the workers, public and the environment during the test. This reproducible method can support nuclear facility operators as a reference method to compare the decontamination factor evaluated by this method to reference values (e.g. safety criteria, national legislation, etc.). Because of the use of a radioactive tracer, some precautions should be applied. Firstly, this method is usually used for ventilation systems with monitoring of gaseous iodine releases in environment in accordance with the national regulations. Secondly, this method is not used to determine the decontamination factor of iodine traps used in ventilation systems with air release in rooms with potential presence of workers (e.g. control room). For those rooms, a non-radioactive method is preferred. This document can apply to installations with low inventory of radioiodine equipped with iodine traps (e.g. small laboratories). In this case, some provisions can be adapted but always in accordance with the national regulations. Finally, this document mainly deals with iodine traps using impregnated activated carbon. However, this method can be used with some adaptations to other solid sorbent as inorganic sorbent (e.g. zeolite – aluminium and silica base usually doped with silver nitrate – or impregnated catalytic supports[11][12]).

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ISO
ISO 16659-3:2026(Main)
Ventilation systems for nuclear facilities — In-situ efficiency test methods for iodine traps with solid sorbent — Part 3: Cyclohexane gas leakage rate method

ISO 16659 series provide different test methods aiming at assessing the performances of radioactive iodine traps in ventilation systems of nuclear facilities. This series deals with iodine traps with solid sorbent, mainly activated and impregnated charcoal, the most common solid sorbents used in ventilation systems of nuclear facilities, as well as other sorbents for special conditions (e.g. high temperature zeolites). ISO 16659-1 provides the general requirements to be applied for all methods of the series. The scope of this document is to provide general and generic requirements for the test method using cyclohexane (C6H12) as a tracer to determine the mechanical leakage rate of iodine trap. This reproducible method can support nuclear operators to compare the result with reference values given in safety reports. Unlike the method of radioactive methyl iodide described in ISO 16659-2, the cyclohexane field test method covered in this document does not directly give a decontamination factor for the iodine trap, but only the iodine trap performance information of an integrity test. Due to the use of the environmentally friendly test reagent of low-toxicity in the field tests, the method is mainly suitable for ventilation systems of those habitable spaces (e.g. main control rooms of nuclear power plants), and performance test of a single iodine trap before its delivery and acceptance. In addition, the method can also be used for iodine traps with activated carbon sampling canister (e.g. deep bed iodine trap Type III and Drawer iodine trap Type II).

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CEN
EN ISO 18090-1:2026(Main)
Radiological protection - Characteristics of reference pulsed radiation - Part 1: Photon radiation (ISO 18090-1:2026)
SIST EN ISO 18090-1:2026

This document is directly applicable to pulsed X-radiation with pulse duration of 0,1 ms up to 10 s. This range covers the whole range used in medical diagnostics at the time of publication. Some specifications can also be applicable for much shorter pulses; one example is the air kerma of one pulse. Such a pulse can be produced, e.g. by X-ray flash units or high-intensity femtosecond-lasers. Other specifications are not applicable for much shorter pulses; one example is the time-dependent behaviour of the air kerma rate. This cannot be measurable for technical reasons as no suitable instrument is available, e.g. for pulses produced by a femtosecond-laser.
This document specifies the characteristics of reference pulsed radiation for calibrating and testing radiation protection dosemeters and dose rate meters with respect to their response to pulsed radiation. At this point, it is only concerned with the characteristics of single pulses. Single pulses are the most difficult for dosemeters to measure. Determining the dose for repeated pulses is easier, but still more difficult than for continuous radiation, i.e. the performance of the dosemeters when measuring repeated pulses lies between these extremes. The radiation characteristics includes the following:
time-dependent behaviour of the air kerma rate of the pulse;
time-dependent behaviour of the X-ray tube high voltage during the pulse;
uniformity of the air kerma rate within a cross-sectional area of the radiation beam;
air kerma of one radiation pulse;
air kerma rate of the radiation pulse;
repetition frequency.
This document does not define new radiation qualities but uses those radiation qualities specified in existing ISO and IEC standards. Instead, this document gives the link between the parameters for pulsed radiation and the parameters for continuous radiation specifying the radiation qualities. It does not specify specific values or series of values for the pulsed radiation field but specifies only those limits for the relevant pulsed radiation parameters that are required for calibrating dosemeters and dose rate meters and for determining their response depending on the said parameters.
The pulse parameters with respect to the phantom-related quantities were determined using conversion coefficients according to ISO 4037 (all parts). This is possible as the radiation qualities specified in existing ISO and IEC standards are used.
A given reference pulsed X-ray facility is characterized by the parameter ranges over which the full specifications and requirements according to this document are met. Therefore, not all reference pulsed X-ray facilities can produce pulses covering the same parameter ranges.

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ISO
ISO 18090-1:2026(Main)
Radiological protection — Characteristics of reference pulsed radiation — Part 1: Photon radiation

This document is directly applicable to pulsed X-radiation with pulse duration of 0,1 ms up to 10 s. This range covers the whole range used in medical diagnostics at the time of publication. Some specifications can also be applicable for much shorter pulses; one example is the air kerma of one pulse. Such a pulse can be produced, e.g. by X-ray flash units or high-intensity femtosecond-lasers. Other specifications are not applicable for much shorter pulses; one example is the time-dependent behaviour of the air kerma rate. This cannot be measurable for technical reasons as no suitable instrument is available, e.g. for pulses produced by a femtosecond-laser. This document specifies the characteristics of reference pulsed radiation for calibrating and testing radiation protection dosemeters and dose rate meters with respect to their response to pulsed radiation. At this point, it is only concerned with the characteristics of single pulses. Single pulses are the most difficult for dosemeters to measure. Determining the dose for repeated pulses is easier, but still more difficult than for continuous radiation, i.e. the performance of the dosemeters when measuring repeated pulses lies between these extremes. The radiation characteristics includes the following: time-dependent behaviour of the air kerma rate of the pulse; time-dependent behaviour of the X-ray tube high voltage during the pulse; uniformity of the air kerma rate within a cross-sectional area of the radiation beam; air kerma of one radiation pulse; air kerma rate of the radiation pulse; repetition frequency. This document does not define new radiation qualities but uses those radiation qualities specified in existing ISO and IEC standards. Instead, this document gives the link between the parameters for pulsed radiation and the parameters for continuous radiation specifying the radiation qualities. It does not specify specific values or series of values for the pulsed radiation field but specifies only those limits for the relevant pulsed radiation parameters that are required for calibrating dosemeters and dose rate meters and for determining their response depending on the said parameters. The pulse parameters with respect to the phantom-related quantities were determined using conversion coefficients according to ISO 4037 (all parts). This is possible as the radiation qualities specified in existing ISO and IEC standards are used. A given reference pulsed X-ray facility is characterized by the parameter ranges over which the full specifications and requirements according to this document are met. Therefore, not all reference pulsed X-ray facilities can produce pulses covering the same parameter ranges.

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ISO
ISO 11933-5:2026(Main)
Components for containment enclosures — Part 5: Penetrations for electrical and fluid circuits

This document specifies selection criteria for, and describes the design characteristics of, the various electrical- and fluid-circuit penetration components mounted on leaktight or shielded containment enclosures. This document is applicable to electrical components, including connectors, fixed or removable wall penetrations, distribution boxes and lighting devices, and fluid components, including fixed or removable wall penetrations, fittings and junctions, and control devices for process or effluent circuits. NOTE The elements constituting the framework of containment enclosures (e.g. metallic walls, framework and transparent panels) are dealt with in ISO 10648-1.

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IEC
IEC 60761-2:2026(Main)
Radiation protection instrumentation - Equipment for continuous monitoring of radioactivity in gaseous effluents - Part 2: Specific requirements for radioactive aerosol monitors including transuranic aerosols

IEC 60761-2:2026 is applicable to equipment intended for simultaneous, delayed or discrete sequential measurement of aerosols in gaseous effluents discharged into the environment.
It is applicable to equipment designed to fulfil the following functions:
- the measurement of the volumetric activity (Bq/m3) of the aerosols in either gaseous effluents or the released total activity of aerosols (Bq), or both;
- the actuation of an alarm signal when either a predetermined volumetric activity or a predetermined total released activity of aerosols is exceeded.
This equipment is intended for measurement over a wide range of activity, including very small quantities in the presence of a much larger natural background. The daughters of 222Rn (radon) and 220Rn (thoron) are naturally occurring aerosols contributing to the natural background.
The objective of this document is to establish specific standard requirements, including technical characteristics and general test conditions, and to give examples of acceptable methods for aerosol effluent monitors.
The general requirements, technical characteristics, test procedures, radiation characteristics, electrical, mechanical, safety and environmental characteristics are given in IEC 60761-1. Unless otherwise stated, these requirements apply to this document.
This International Standard is to be used in conjunction with IEC 60761-1:2002. This third edition cancels and replaces the second edition published in 2002. This edition includes the following significant technical changes with respect to the previous edition:
- more precise tests for air-flow were added:
- sampled volume correctness;
- flow-rate robustness;
- uncertainties have been taken into account for the reference response test;
- addition of tests against aerosol granulometry variation;
- creating a uniform functionality test for all environmental, electromagnetic and mechanical tests and a requirement for the coefficient of variation of each nominal mean reading.

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SIST
SIST EN IEC 62387:2022/A12:2026(Amendment)
Radiation protection instrumentation - Dosimetry systems with integrating passive detectors for individual, workplace and environmental monitoring of photon and beta radiation
EN IEC 62387:2022/A12:2026

This document applies to all kinds of passive dosimetry systems that are used for measuring:
– the personal dose equivalent Hp(10) (for individual whole body monitoring),
– the personal dose equivalent Hp(3) (for individual eye lens monitoring),
– the personal dose equivalent Hp(0,07) (for both individual whole body skin and local skin for extremity monitoring),
– the ambient dose equivalent H*(10) (for workplace and environmental monitoring),
– the directional dose equivalent H'(3) (for workplace and environmental monitoring), or
– the directional dose equivalent H'(0,07) (for workplace and environmental monitoring).
This document applies to dosimetry systems that measure external photon and/or beta radiation in the dose range between 0,01 mSv and 10 Sv.

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CLC
EN IEC 62387:2022/A12:2026(Amendment)
Radiation protection instrumentation - Dosimetry systems with integrating passive detectors for individual, workplace and environmental monitoring of photon and beta radiation
SIST EN IEC 62387:2022/A12:2026

This document applies to all kinds of passive dosimetry systems that are used for measuring: – the personal dose equivalent Hp(10) (for individual whole body monitoring), – the personal dose equivalent Hp(3) (for individual eye lens monitoring), – the personal dose equivalent Hp(0,07) (for both individual whole body skin and local skin for extremity monitoring), – the ambient dose equivalent H*(10) (for workplace and environmental monitoring), – the directional dose equivalent H'(3) (for workplace and environmental monitoring), or – the directional dose equivalent H'(0,07) (for workplace and environmental monitoring). This document applies to dosimetry systems that measure external photon and/or beta radiation in the dose range between 0,01 mSv and 10 Sv.

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SIST
SIST EN IEC 61526:2026(Main)
Radiation protection instrumentation - Measurement of personal dose equivalents for X, gamma, neutron and beta radiations - Active personal dosemeters (IEC 61526:2024)
EN IEC 61526:2026

This document applies to personal dosemeters with the following characteristics:
a)   They are worn on the trunk, close to the eye, or on the extremities.
b)   They measure the personal dose equivalents Hp(10), Hp(3), and Hp(0,07), from external X and gamma, neutron (not for Hp(3)), and beta radiations, and may measure the respective personal dose equivalent rates for the same radiations (for alarming purposes).
c)   They have a digital indication. This indication may or may not be attached.
d)   They have alarm functions for the personal dose equivalents or personal dose equivalent rates except for hybrid dosemeters. For hybrid dosemeters an alarm function for the personal dose equivalents shall be implemented in the associated readout system.

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CLC
EN IEC 61526:2026(Main)
Radiation protection instrumentation - Measurement of personal dose equivalents for X, gamma, neutron and beta radiations - Active personal dosemeters
SIST EN IEC 61526:2026

This document applies to personal dosemeters with the following characteristics: a) They are worn on the trunk, close to the eye, or on the extremities. b) They measure the personal dose equivalents Hp(10), Hp(3), and Hp(0,07), from external X and gamma, neutron (not for Hp(3)), and beta radiations, and may measure the respective personal dose equivalent rates for the same radiations (for alarming purposes). c) They have a digital indication. This indication may or may not be attached. d) They have alarm functions for the personal dose equivalents or personal dose equivalent rates except for hybrid dosemeters. For hybrid dosemeters an alarm function for the personal dose equivalents shall be implemented in the associated readout system.

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IEC
IEC 61577-6:2026(Main)
Radiation protection instrumentation - Radon and radon decay product measuring instruments - Part 6: Passive integrating radon measurement system using solid-state nuclear track detectors

IEC 61577-6:2026 describes the specific requirements for instruments measuring the exposure to airborne radon (222Rn) outdoors and indoors. The exposure is the time-integrated radon activity concentration in air accumulated over the exposure period.
This document applies to radon integration measurement systems equipped with solid-state nuclear track detectors (SSNTD) installed in an enclosed volume. The air containing 222Rn enters the volume by diffusionIEC 61577 describes the specific requirements for instruments measuring the exposure to airborne radon (222Rn) outdoors and indoors. The exposure is the time-integrated radon activity concentration in air accumulated over the exposure period.
This document applies to radon integration measurement systems equipped with solid-state nuclear track detectors (SSNTD) installed in an enclosed volume. The air containing 222Rn enters the volume by diffusion

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SIST
SIST EN 50413:2021/A1:2026(Amendment)
Basic standard on measurement and calculation procedures for human exposure to electric, magnetic and electromagnetic fields (0 Hz - 300 GHz)
EN 50413:2019/A1:2025

This document provides general methods for measurement and calculation of quantities associated with human exposure to electromagnetic fields in the frequency range from 0 Hz to 300 GHz. It is intended specifically to be used for the assessment of emissions from products and comparison of these with the exposure limits for the general public given in Council Recommendation 1999/519/EC, and those given for workers in Directive 2013/35/EU, as appropriate. It also is intended to be used for assessment of human exposure to electromagnetic fields in the workplace to determine compliance with the requirements of Directive 2013/35/EU.
This standard deals with quantities that can be measured or calculated external to the body, notably electric and magnetic field strength or power density, and includes the measurement and calculation of quantities inside the body that form the basis for protection guidelines. In particular the standard provides information on:
- definitions and terminology,
- characteristics of electromagnetic fields,
- measurement of exposure quantities,
- instrumentation requirements,
- methods of calibration,
- measurement techniques and procedures for evaluating exposure,
- calculation methods for exposure assessment.
Where an applicable electromagnetic field standard specific to a product or technology exists it is expected to be used rather than this document. EN 62311:-, Table 1 gives a list of relevant standards.

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IEC
ISO/IEC 11801-1:2017(Main)
Information technology - Generic cabling for customer premises - Part 1: General requirements

ISO/IEC 11801-1:2017(E) This document specifies a multi-vendor cabling system which may be implemented with material from single or multiple sources. This part of ISO/IEC 11801 defines requirements that are common to the other parts of the ISO/IEC 11801 series. Cabling specified by this document supports a wide range of services including voice, data, and vido that may also incorporate the supply of power.
The contents of the corrigendum of April 2018 have been included in this copy.

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SIST
SIST EN 50566:2018/A2:2025(Amendment)
Product standard to demonstrate the compliance of wireless communication devices with the basic restrictions and exposure limit values related to human exposure to electromagnetic fields in the frequency range from 30 MHz to 6 GHz: hand-held and body mounted devices in close proximity to the human body
EN 50566:2017/A2:2025
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SIST
SIST EN ISO 21243:2025(Main)
Radiation protection - Performance criteria for laboratories performing initial cytogenetic dose assessment of mass casualties in radiological or nuclear emergencies - General principles and application to dicentric assay (ISO 21243:2022)
EN ISO 21243:2025

The purpose of this document is to give an overview of the minimum requirements for performing the dicentric assay with quality control measures using mitogen stimulated peripheral blood lymphocytes for initial assessment of individuals involved in a mass casualty scenario. The dicentric assay is the use of chromosome damage to quickly estimate approximate radiation doses received by individuals in order to supplement the early clinical categorization of casualties.
This document focuses on the organizational and operational aspects of applying the dicentric assay in an initial assessment mode. The technical aspects of the dicentric assay can be found in ISO 19238.
This document is applicable either to an experienced biological dosimetry laboratory working alone or to a network of collaborating laboratories (as defined in Clause 7).

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SIST
SIST EN ISO 7753:2025(Main)
Nuclear criticality safety - Use of criticality accident alarm systems for operations (ISO 7753:2023)
EN ISO 7753:2025

This document provides requirements and guidance regarding the use of CAAS for operations of a nuclear facility. Requirements and guidance on CAAS design are provided in the IEC 60860.
This document is applicable to operations with fissile materials outside nuclear reactors but within the boundaries of nuclear establishments.
This document applies when a need for CAAS has been established. Information about the need for CAAS is given in Annex C.
This document does not include details of administrative steps, which are considered to be activities of a robust management system (ISO 14943 provides details of administrative steps).
Details of nuclear accident dosimetry and personnel exposure evaluations are not within the scope of this document.
This document is concerned with gamma and neutron radiation rate-sensing systems. Specific detection criteria can also be met with integrating systems; systems detecting either neutron or gamma radiation can also be used. Equivalent considerations then apply.

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SIST
SIST EN ISO 16646:2025(Main)
Fusion installations - Criteria for the design and operation of confinement and ventilation systems of tritium fusion facilities and fusion fuel handling facilities (ISO 16646:2024)
EN ISO 16646:2025

This document specifies the applicable requirements related to the design and the operation of confinement and ventilation systems for fusion facilities for tritium fuels and tritium fuel handling facilities specific for fusion applications for peaceful purposes using high tritium inventories, as well as for their specialized buildings such as hot cells, examination laboratories, emergency management centres, radioactive waste treatment and storage facilities.
In most countries, a tritium quantity is declared as high for tritium inventories higher than a range of 10 g to 100 g. In the tritium fusion facilities in the scope of this document, the tritium inventory is deemed to be higher than this range for the whole site.
This document applies especially to confinement and ventilation systems that ensure the safety function of nuclear facilities involved in nuclear fusion with the goal to protect the workers, the public and the environment from the dissemination of radioactive contamination originating from the operation of these installations, and in particular from airborne tritium contamination with adequate confinement systems.

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SIST
SIST EN ISO 22188:2025(Main)
Monitoring for inadvertent movement and illicit trafficking of radioactive material (ISO 22188:2023)
EN ISO 22188:2025

This document specifies methods and means of monitoring for inadvertent movement and illicit trafficking of radioactive material. It provides guidelines on the use of both stationary and portable, for example hand-held, instruments to monitor for radiation signatures from radioactive material. Emphasis is placed on the operational aspects, i.e., requirements derived for monitoring of traffic and commodities mainly at border-crossing facilities. Although the term border is used repeatedly in this document, it is meant to apply not only to international land borders but also maritime ports, airports, and similar locations where goods or individuals are being checked. This document does not specifically address the issue of detection of radioactive materials at recycling facilities, although it is recognized that transboundary movement of metals for recycling occurs, and that monitoring of scrap metals might be done at the borders of a state.
This document is applicable to
—    regulatory bodies and other competent authorities seeking guidance on implementation of action plans to combat illicit trafficking,
—    law enforcement agencies, for example border guards, to obtain guidelines on recommended monitoring procedures,
—    equipment manufacturers in order to understand minimum requirements derived from operational necessities according to this document, and
—    end-users of radiation detection equipment applicable to this document.

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SIST
SIST EN ISO 15382:2025(Main)
Radiological protection - Procedures for monitoring the dose to the lens of the eye, the skin and the extremities (ISO 15382:2025)
EN ISO 15382:2025

This document provides procedures for monitoring the dose to the skin, the extremities, and the lens of the eye. It gives guidance on how to decide if such dosemeters are needed and to ensure that individual monitoring is appropriate to the nature of the exposure, taking practical considerations into account.
This document specifies procedures for individual monitoring of radiation exposure of the skin of the body, extremities (skin of the hands, fingers, wrists, forearms including elbow, lower leg including patella, feet and ankles), and lens of the eye in planned exposure situations. It covers practices which involve a risk of exposure to photons in the range of 8 keV to 10 MeV, electrons and positrons in the range of 0,07 MeV to 1,2 MeV mean beta energies being equivalent to 0,22 MeV and 3,6 MeV beta maximum energy - in accordance to the ISO 6980 series, and neutrons in the range of thermal to 20 MeV.
This document gives guidance for the design of a monitoring programme to ensure compliance with legal individual dose limits. It refers to the appropriate operational dose quantities, and it gives guidance on the type and frequency of individual monitoring and the type and positioning of the dosemeter. Finally, different approaches to assess and analyse skin, extremity, and lens of the eye doses are given.
It is not in the scope of this document to consider exposure due to alpha radiation fields.
NOTE 1        The requirements for the monitoring of the occupational exposure may be given in national regulations.
NOTE 2        Dose to the lens of the eye due to intake of tritium is not in the scope of this document. Moreover, the situation of the workers that work in contaminated atmosphere and can have alpha and/or radon eye lens dose is also not in the scope.

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CEN
EN ISO 7753:2025(Main)
Nuclear criticality safety - Use of criticality accident alarm systems for operations (ISO 7753:2023)
SIST EN ISO 7753:2025

This document provides requirements and guidance regarding the use of CAAS for operations of a nuclear facility. Requirements and guidance on CAAS design are provided in the IEC 60860.
This document is applicable to operations with fissile materials outside nuclear reactors but within the boundaries of nuclear establishments.
This document applies when a need for CAAS has been established. Information about the need for CAAS is given in Annex C.
This document does not include details of administrative steps, which are considered to be activities of a robust management system (ISO 14943 provides details of administrative steps).
Details of nuclear accident dosimetry and personnel exposure evaluations are not within the scope of this document.
This document is concerned with gamma and neutron radiation rate-sensing systems. Specific detection criteria can also be met with integrating systems; systems detecting either neutron or gamma radiation can also be used. Equivalent considerations then apply.

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CEN
EN ISO 22188:2025(Main)
Monitoring for inadvertent movement and illicit trafficking of radioactive material (ISO 22188:2023)
SIST EN ISO 22188:2025

This document specifies methods and means of monitoring for inadvertent movement and illicit trafficking of radioactive material. It provides guidelines on the use of both stationary and portable, for example hand-held, instruments to monitor for radiation signatures from radioactive material. Emphasis is placed on the operational aspects, i.e., requirements derived for monitoring of traffic and commodities mainly at border-crossing facilities. Although the term border is used repeatedly in this document, it is meant to apply not only to international land borders but also maritime ports, airports, and similar locations where goods or individuals are being checked. This document does not specifically address the issue of detection of radioactive materials at recycling facilities, although it is recognized that transboundary movement of metals for recycling occurs, and that monitoring of scrap metals might be done at the borders of a state.
This document is applicable to
—    regulatory bodies and other competent authorities seeking guidance on implementation of action plans to combat illicit trafficking,
—    law enforcement agencies, for example border guards, to obtain guidelines on recommended monitoring procedures,
—    equipment manufacturers in order to understand minimum requirements derived from operational necessities according to this document, and
—    end-users of radiation detection equipment applicable to this document.

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CEN
EN ISO 16646:2025(Main)
Fusion installations - Criteria for the design and operation of confinement and ventilation systems of tritium fusion facilities and fusion fuel handling facilities (ISO 16646:2024)
SIST EN ISO 16646:2025

This document specifies the applicable requirements related to the design and the operation of confinement and ventilation systems for fusion facilities for tritium fuels and tritium fuel handling facilities specific for fusion applications for peaceful purposes using high tritium inventories, as well as for their specialized buildings such as hot cells, examination laboratories, emergency management centres, radioactive waste treatment and storage facilities.
In most countries, a tritium quantity is declared as high for tritium inventories higher than a range of 10 g to 100 g. In the tritium fusion facilities in the scope of this document, the tritium inventory is deemed to be higher than this range for the whole site.
This document applies especially to confinement and ventilation systems that ensure the safety function of nuclear facilities involved in nuclear fusion with the goal to protect the workers, the public and the environment from the dissemination of radioactive contamination originating from the operation of these installations, and in particular from airborne tritium contamination with adequate confinement systems.
The types of confinement systems for other facilities are covered by ISO 26802 for fission nuclear reactors, by ISO 17873 for facilities other than fission nuclear reactors and by ISO 16647 for nuclear worksite and for nuclear installations under decommissioning. The facilities covered by these three standards, notably ISO 17873, include tritium as a radioactive material among the ones to be confined, but tritium is not their driver of the risks for workers and for members of the public. Nevertheless, the tritium quantities and risks from fusion facilities create specificities for a specific standard (e.g. in fusion facilities, tritium is the driver of routine and accident consequences). Therefore, the scope of this document does not cover the other facilities involved in tritium releases (ISO 17873, ISO 16647 and ISO 26802), even though these other facilities create tritium releases (e.g. non-reactor fission facilities, tritium laboratories, tritium removal facilities from fission plants, tritium defence facilities).

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CEN
EN ISO 21243:2025(Main)
Radiation protection - Performance criteria for laboratories performing initial cytogenetic dose assessment of mass casualties in radiological or nuclear emergencies - General principles and application to dicentric assay (ISO 21243:2022)
SIST EN ISO 21243:2025

The purpose of this document is to give an overview of the minimum requirements for performing the dicentric assay with quality control measures using mitogen stimulated peripheral blood lymphocytes for initial assessment of individuals involved in a mass casualty scenario. The dicentric assay is the use of chromosome damage to quickly estimate approximate radiation doses received by individuals in order to supplement the early clinical categorization of casualties.
This document focuses on the organizational and operational aspects of applying the dicentric assay in an initial assessment mode. The technical aspects of the dicentric assay can be found in ISO 19238.
This document is applicable either to an experienced biological dosimetry laboratory working alone or to a network of collaborating laboratories (as defined in Clause 7).

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ISO
ISO 18518:2025(Main)
Magnetic fusion facilities — Requirements for the safety systems raised by the application of the superconducting technology

This document specifies requirements concerning safety systems raised by the application of superconducting magnets in fusion facilities. Safety systems include confinement systems (both static and dynamic types), shielding barriers, penetrations, and supporting systems such as instrumentation and control. The requirements are applicable to both normal and abnormal operation of a fusion facility. For instance, the radiation protection shall be adequate in order to permit the hands-on operation to the electronics and parts for inspection, maintenance and replacement; the hazards associated with superconducting magnets, such as the loss of superconductivity (quench), Paschen breakdown following helium and voltage leakage, shall be prevented from breaching the integrity of safety systems. This document will facilitate the design and assessment of the safety systems in a fusion facility with superconducting magnets for all configurations, such as tokamak, stellarator and magneto-inertial fusion devices. Based on the advancement and maturity of the tokamak configuration, this document outlines safety requirements mostly derived from the tokamak configuration but also applicable to other configurations and layouts that may be adopted by future fusion devices.

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ISO
ISO 24427:2025(Main)
Radiological protection — Medical proton accelerators — Requirements and recommendations for shielding design and evaluation

This document is applicable to the radiation shielding design and evaluation work for medical proton accelerators of proton energies ranging from 70 MeV to 250 MeV, with subsystems such as beam transport system and nozzle components. The radiation protection recommendations given in this document cover the aspects relating to regulations, shielding design goals and other design criteria, role of the manufacturers, of the radiation protection officer or qualified expert, the medical physicist, the licensee and interactions between them, sources and radiations around a proton accelerator, shielding for accelerators and its subsystems (including shielding materials and transmission values, calculations for various room configurations, duct impact on radiation protection) and the radiological measurements. FLASH proton therapy is not covered by this document. NOTE 1 Annex A provides a list of the most used Monte-Carlo codes for shielding calculation. NOTE 2 Annex B provides the analytical methods and the corresponding necessary data for shielding calculation. NOTE 3 Annex C provides a set of examples on shielding calculation of barriers, maze and skyshine problems. NOTE 4 Annex D provides radiation shielding consideration on special topics.

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CEN
EN ISO 15382:2025(Main)
Radiological protection - Procedures for monitoring the dose to the lens of the eye, the skin and the extremities (ISO 15382:2025)
SIST EN ISO 15382:2025

This document provides procedures for monitoring the dose to the skin, the extremities, and the lens of the eye. It gives guidance on how to decide if such dosemeters are needed and to ensure that individual monitoring is appropriate to the nature of the exposure, taking practical considerations into account.
This document specifies procedures for individual monitoring of radiation exposure of the skin of the body, extremities (skin of the hands, fingers, wrists, forearms including elbow, lower leg including patella, feet and ankles), and lens of the eye in planned exposure situations. It covers practices which involve a risk of exposure to photons in the range of 8 keV to 10 MeV, electrons and positrons in the range of 0,07 MeV to 1,2 MeV mean beta energies being equivalent to 0,22 MeV and 3,6 MeV beta maximum energy - in accordance to the ISO 6980 series, and neutrons in the range of thermal to 20 MeV.
This document gives guidance for the design of a monitoring programme to ensure compliance with legal individual dose limits. It refers to the appropriate operational dose quantities, and it gives guidance on the type and frequency of individual monitoring and the type and positioning of the dosemeter. Finally, different approaches to assess and analyse skin, extremity, and lens of the eye doses are given.
It is not in the scope of this document to consider exposure due to alpha radiation fields.
NOTE 1        The requirements for the monitoring of the occupational exposure may be given in national regulations.
NOTE 2        Dose to the lens of the eye due to intake of tritium is not in the scope of this document. Moreover, the situation of the workers that work in contaminated atmosphere and can have alpha and/or radon eye lens dose is also not in the scope.

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ISO
ISO 15382:2025(Main)
Radiological protection — Procedures for monitoring the dose to the lens of the eye, the skin and the extremities

This document provides procedures for monitoring the dose to the skin, the extremities, and the lens of the eye. It gives guidance on how to decide if such dosemeters are needed and to ensure that individual monitoring is appropriate to the nature of the exposure, taking practical considerations into account. This document specifies procedures for individual monitoring of radiation exposure of the skin of the body, extremities (skin of the hands, fingers, wrists, forearms including elbow, lower leg including patella, feet and ankles), and lens of the eye in planned exposure situations. It covers practices which involve a risk of exposure to photons in the range of 8 keV to 10 MeV, electrons and positrons in the range of 0,07 MeV to 1,2 MeV mean beta energies being equivalent to 0,22 MeV and 3,6 MeV beta maximum energy - in accordance to the ISO 6980 series, and neutrons in the range of thermal to 20 MeV. This document gives guidance for the design of a monitoring programme to ensure compliance with legal individual dose limits. It refers to the appropriate operational dose quantities, and it gives guidance on the type and frequency of individual monitoring and the type and positioning of the dosemeter. Finally, different approaches to assess and analyse skin, extremity, and lens of the eye doses are given. It is not in the scope of this document to consider exposure due to alpha radiation fields. NOTE 1 The requirements for the monitoring of the occupational exposure may be given in national regulations. NOTE 2 Dose to the lens of the eye due to intake of tritium is not in the scope of this document. Moreover, the situation of the workers that work in contaminated atmosphere and can have alpha and/or radon eye lens dose is also not in the scope.

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    38 pages
    French language
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ISO
ISO 13165-4:2025(Main)
Water quality — Radium-226 — Part 4: Test method using alpha spectrometry

This document specifies methods to determine 226Ra by alpha spectrometry in supply water, drinking water, rainwater, surface and ground water, marine water, as well as cooling water, industrial water, domestic, and industrial wastewater after proper sampling, handling and test sample preparation. The detection limit depends on the sample volume, the instrument used, the background count rate, the detection efficiency, the counting time and the chemical yield. The detection limit of the methods described in this document, using currently available alpha spectrometry apparatus, is equal to or lesser than 3 mBq·l−1 (or mBq·kg−1), which is lower than the WHO criteria for safe consumption of drinking water (1 Bq·l−1)[ REF Reference_ref_12 \r \h 4 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310032000000 ]. This value can typically be achieved with a counting time of 48 h for a test sample volume of 40 ml. The method described in this document is applicable in the event of an emergency situation. Filtration of the test sample is necessary for the methods described in this document if suspended solids are present. The analysis of 226Ra adsorbed to suspended matter is not covered by this method, because it requires a mineralization step. In this case, the measurement is made on the different phases obtained. The final activity is the sum of all the measured activity concentrations. It is the user’s responsibility to ensure the validity of this test method for the water samples tested.

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SIST
SIST EN IEC 62232:2025(Amendment)
Determination of RF field strength, power density and SAR in the vicinity of base stations for the purpose of evaluating human exposure
EN IEC 62232:2025

IEC 62232:2025 provides methods for the determination of RF field strength, power density and specific absorption rate (SAR) in the vicinity of base stations (BS) for the purpose of evaluating human exposure.
This document:
a) considers intentionally radiating BS which transmit on one or more antennas using one or more frequencies in the range 110 MHz to 300 GHz;
b) considers the impact of ambient sources on RF exposure at least in the 100 kHz to 300 GHz frequency range;
c) specifies the methods to be used for RF exposure evaluation for compliance assessment applications, namely:
1) product compliance – determination of compliance boundary information for a BS product before it is placed on the market;
2) product installation compliance – determination of the total RF exposure levels in accessible areas from a BS product and other relevant sources before the product is put into operation;
3) in-situ RF exposure assessment – measurement of in-situ RF exposure levels in the vicinity of a BS installation after the product has been taken into operation;
d) specifies how to perform RF exposure assessment based on the actual maximum approach;
e) describes several RF field strength, power density, and SAR measurement and computation methodologies with guidance on their applicability to address both the in-situ evaluation of installed BS and laboratory-based evaluations;
f) describes how surveyors establish their specific evaluation procedures appropriate for their evaluation purpose;
g) provides guidance on how to report, interpret and compare results from different evaluation methodologies and, where the evaluation purpose requires it, determine a justified decision against a limit value;
h) provides methods for the RF exposure assessment of BS using time-varying beam-steering technologies such as new radio (NR) BS using massive multiple input multiple output (MIMO).
NOTE 1 Practical implementation case studies are provided as examples in the companion Technical Report IEC TR 62669 [5].
NOTE 2 Although the current BS product types have been specified to operate up to 200 GHz (see, for example, [6] and [7]), the upper frequency of 300 GHz is consistent with applicable exposure limits.
NOTE 3 The lower frequency considered for ambient sources, 100 kHz, is derived from ICNIRP-1998 [2] and ICNIRP-2020 [1]. However, some applicable exposure guidelines require ambient fields to be evaluated as low as 3 kHz, e.g. Safety Code 6 [4] and IEEE Std C95.1-2019 [3].
NOTE 4 Specification of appropriate RF exposure mitigation measures such as signage, access control, and training are beyond the scope of this document. It is possible to refer to the applicable regulations or recommended practices on these topics.
NOTE 5 While this document is based on the current international consensus about the best engineering practice for assessing the compliance of RF exposure with the applicable exposure limits, it is possible that national regulatory agencies specify different requirements. The entity conducting an RF exposure assessment needs to be aware of the applicable regulations.
This fourth edition cancels and replaces the third edition published in 2022. It includes corrections of obvious errors and text improvements on the third edition in order to bring more clarity in the description of the assessment methods and avoid misinterpretations. This edition has the same technical content as the third edition.

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CLC
EN IEC 62232:2025(Main)
Determination of RF field strength, power density and SAR in the vicinity of base stations for the purpose of evaluating human exposure
SIST EN IEC 62232:2025

IEC 62232:2025 provides methods for the determination of RF field strength, power density and specific absorption rate (SAR) in the vicinity of base stations (BS) for the purpose of evaluating human exposure. This document: a) considers intentionally radiating BS which transmit on one or more antennas using one or more frequencies in the range 110 MHz to 300 GHz; b) considers the impact of ambient sources on RF exposure at least in the 100 kHz to 300 GHz frequency range; c) specifies the methods to be used for RF exposure evaluation for compliance assessment applications, namely: 1) product compliance – determination of compliance boundary information for a BS product before it is placed on the market; 2) product installation compliance – determination of the total RF exposure levels in accessible areas from a BS product and other relevant sources before the product is put into operation; 3) in-situ RF exposure assessment – measurement of in-situ RF exposure levels in the vicinity of a BS installation after the product has been taken into operation; d) specifies how to perform RF exposure assessment based on the actual maximum approach; e) describes several RF field strength, power density, and SAR measurement and computation methodologies with guidance on their applicability to address both the in-situ evaluation of installed BS and laboratory-based evaluations; f) describes how surveyors establish their specific evaluation procedures appropriate for their evaluation purpose; g) provides guidance on how to report, interpret and compare results from different evaluation methodologies and, where the evaluation purpose requires it, determine a justified decision against a limit value; h) provides methods for the RF exposure assessment of BS using time-varying beam-steering technologies such as new radio (NR) BS using massive multiple input multiple output (MIMO). NOTE 1 Practical implementation case studies are provided as examples in the companion Technical Report IEC TR 62669 [5]. NOTE 2 Although the current BS product types have been specified to operate up to 200 GHz (see, for example, [6] and [7]), the upper frequency of 300 GHz is consistent with applicable exposure limits. NOTE 3 The lower frequency considered for ambient sources, 100 kHz, is derived from ICNIRP-1998 [2] and ICNIRP-2020 [1]. However, some applicable exposure guidelines require ambient fields to be evaluated as low as 3 kHz, e.g. Safety Code 6 [4] and IEEE Std C95.1-2019 [3]. NOTE 4 Specification of appropriate RF exposure mitigation measures such as signage, access control, and training are beyond the scope of this document. It is possible to refer to the applicable regulations or recommended practices on these topics. NOTE 5 While this document is based on the current international consensus about the best engineering practice for assessing the compliance of RF exposure with the applicable exposure limits, it is possible that national regulatory agencies specify different requirements. The entity conducting an RF exposure assessment needs to be aware of the applicable regulations. This fourth edition cancels and replaces the third edition published in 2022. It includes corrections of obvious errors and text improvements on the third edition in order to bring more clarity in the description of the assessment methods and avoid misinterpretations. This edition has the same technical content as the third edition.

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SIST EN IEC 60601-2-68:2025(Amendment)
Medical electrical equipment - Part 2-68: Particular requirements for the basic safety and essential performance of X-ray-based image-guided radiotherapy equipment for use with electron accelerators, light ion beam therapy equipment and radionuclide beam therapy equipment (IEC 60601-2-68:2025)
EN IEC 60601-2-68:2025

IEC 60601-2-68:2025 applies to the BASIC SAFETY and ESSENTIAL PERFORMANCE of X-ray based IMAGE-GUIDED RADIOTHERAPY equipment for use with EXTERNAL BEAM EQUIPMENT (EBE). This document covers safety aspects of kilovoltage (kV) and megavoltage (MV) X-ray imaging devices integrated in a specified geometrical relationship with EBE for the purpose of IGRT. It covers aspects of communication and relationships between the EXTERNAL BEAM EQUIPMENT and X-ray imaging devices, attached or not directly attached to, but in the same RADIATION shielded area as, and dedicated for use only with, the EXTERNAL BEAM EQUIPMENT. This document deals with equipment for OFFLINE X-IGRT, ONLINE X-IGRT and REAL-TIME X-IGRT. It covers procedures to reduce the risk of over-reliance on the X-IGRT EBE SYSTEM. For example, in the case of ONLINE X-IGRT, the MANUFACTURER will provide an interactive interface for user interaction with the correction suggested by the system. This document does not apply to CT SCANNERS, X-RAY EQUIPMENT for RADIOGRAPHY, and X-RAY EQUIPMENT for RADIOSCOPY, which are not intended for use for IGRT. Requirements that are being tested according to another standard can be identified by the manufacturer and if equivalent do not require retesting, instead evidence can refer to the CT SCANNER, X-RAY EQUIPMENT for RADIOGRAPHY, or X-RAY EQUIPMENT for RADIOSCOPY EQUIPMENT manufacturer's providing compliance statements or test reports. If the X-IGRT EQUIPMENT is combined with an MEE, any requirement that is the same for the X-IGRT EQUIPMENT and the MEE, such as a PATIENT POSITIONER, is not required to be tested twice, but can be accepted as tested by the MEE. This document applies for X-ray equipment for radiography, radioscopy, and COMPUTER tomography used for IGRT. If a clause or subclause is specifically intended to be applicable to X-IGRT EBE SYSTEMS, the content of that clause or subclause will say so. Where that is not the case, the clause or subclause applies only to X-IGRT EQUIPMENT.
This document, with the inclusion of TYPE TESTS and SITE TESTS, applies respectively to the MANUFACTURER and some installation aspects of X-IGRT EBE SYSTEMS intended to be:
• for NORMAL USE, operated under the authority of the RESPONSIBLE ORGANIZATION by QUALIFIED PERSONS having the required skills for a particular medical application, for particular specified clinical purposes, e.g., STATIONARY RADIOTHERAPY or MOVING BEAM RADIOTHERAPY,
• maintained in accordance with the recommendations given in the INSTRUCTIONS FOR USE, and
• subject to regular quality assurance performance and calibration checks by a QUALIFIED PERSON.
IEC 80601-2-68:2024 cancels and replaces the first edition published in 2014. This edition constitutes a technical revision.
This edition includes the following significant technical changes with respect to the previous edition:
a) alignment with the new editions of the relevant standards:
– IEC 60601-2-1:2020;
– IEC 60601-2-44:2009, IEC 60601-2-44:2009/AMD1:2012 and IEC 60601-2-44:2009/AMD2:2016;
– IEC 60601-2-64:2014;
b) clarification of the use of IEC 60601-2-68 for CT SCANNERS, X-RAY EQUIPMENT for RADIOGRAPHY and RADIOSCOPY used in the same room with an EXTERNAL BEAM EQUIPMENT (EBE);
c) introduction of updated requirements related to MECHANICAL HAZARDS, RADIATION HAZARDS, PROGRAMMABLE ELECTRICAL MEDICAL SYSTEMS (PEMS), ACCOMPANYING DOCUMENTATION of an ME SYSTEM, and REMOTE OPERATION.

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IEC
IEC 62232:2025(Amendment)
Determination of RF field strength, power density and SAR in the vicinity of base stations for the purpose of evaluating human exposure

IEC 62232:2025 provides methods for the determination of RF field strength, power density and specific absorption rate (SAR) in the vicinity of base stations (BS) for the purpose of evaluating human exposure.
This document:
a) considers intentionally radiating BS which transmit on one or more antennas using one or more frequencies in the range 110 MHz to 300 GHz;
b) considers the impact of ambient sources on RF exposure at least in the 100 kHz to 300 GHz frequency range;
c) specifies the methods to be used for RF exposure evaluation for compliance assessment applications, namely:
1) product compliance – determination of compliance boundary information for a BS product before it is placed on the market;
2) product installation compliance – determination of the total RF exposure levels in accessible areas from a BS product and other relevant sources before the product is put into operation;
3) in-situ RF exposure assessment – measurement of in-situ RF exposure levels in the vicinity of a BS installation after the product has been taken into operation;
d) specifies how to perform RF exposure assessment based on the actual maximum approach;
e) describes several RF field strength, power density, and SAR measurement and computation methodologies with guidance on their applicability to address both the in-situ evaluation of installed BS and laboratory-based evaluations;
f) describes how surveyors establish their specific evaluation procedures appropriate for their evaluation purpose;
g) provides guidance on how to report, interpret and compare results from different evaluation methodologies and, where the evaluation purpose requires it, determine a justified decision against a limit value;
h) provides methods for the RF exposure assessment of BS using time-varying beam-steering technologies such as new radio (NR) BS using massive multiple input multiple output (MIMO).
NOTE 1 Practical implementation case studies are provided as examples in the companion Technical Report IEC TR 62669 [5].
NOTE 2 Although the current BS product types have been specified to operate up to 200 GHz (see, for example, [6] and [7]), the upper frequency of 300 GHz is consistent with applicable exposure limits.
NOTE 3 The lower frequency considered for ambient sources, 100 kHz, is derived from ICNIRP-1998 [2] and ICNIRP-2020 [1]. However, some applicable exposure guidelines require ambient fields to be evaluated as low as 3 kHz, e.g. Safety Code 6 [4] and IEEE Std C95.1-2019 [3].
NOTE 4 Specification of appropriate RF exposure mitigation measures such as signage, access control, and training are beyond the scope of this document. It is possible to refer to the applicable regulations or recommended practices on these topics.
NOTE 5 While this document is based on the current international consensus about the best engineering practice for assessing the compliance of RF exposure with the applicable exposure limits, it is possible that national regulatory agencies specify different requirements. The entity conducting an RF exposure assessment needs to be aware of the applicable regulations.
This fourth edition cancels and replaces the third edition published in 2022. It includes corrections of obvious errors and text improvements on the third edition in order to bring more clarity in the description of the assessment methods and avoid misinterpretations. This edition has the same technical content as the third edition.

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SIST
SIST EN ISO 20553:2025(Main)
Radiation protection - Monitoring of workers occupationally exposed to a risk of internal contamination with radioactive material (ISO 20553:2025)
EN ISO 20553:2025

This document specifies the minimum requirements for the design of programmes to monitor workers exposed to the risk of internal contamination by radioactive material and establishes principles for the development of compatible goals and requirements for monitoring programmes.
This document specifies the
a)       purposes of monitoring and monitoring programmes,
b)       description of the different categories of monitoring programmes,
c)        quantitative criteria for conducting monitoring programmes,
d)       suitable monitoring methods and criteria for their selection,
e)       information that has to be collected for the design of a monitoring programme,
f)         general requirements for monitoring programmes (e.g. detection limits, tolerated uncertainties),
g)       frequencies of measurements calculated using the ICRP Occupational Intakes of Radionuclides (OIR) series,
h)       individual monitoring in specific cases (intake of actinides, intake via a wound and intake through the intact skin),
i)         quality assurance, and
j)         documentation, reporting and record-keeping.
This document does not apply to
—     the monitoring of exposure to radon and its radioactive decay products,
—     detailed descriptions of measuring methods and techniques,
—     detailed procedures for in vivo measurements and in vitro analysis,
—     interpretation of measurements results in terms of dose,
—     biokinetic data and mathematical models for converting measured activities into absorbed dose, equivalent dose and effective dose,
—     the investigation of the causes or implications of an exposure or intake.

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CEN
EN ISO 20553:2025(Main)
Radiation protection - Monitoring of workers occupationally exposed to a risk of internal contamination with radioactive material (ISO 20553:2025)
SIST EN ISO 20553:2025

This document specifies the minimum requirements for the design of programmes to monitor workers exposed to the risk of internal contamination by radioactive material and establishes principles for the development of compatible goals and requirements for monitoring programmes.
This document specifies the
a)       purposes of monitoring and monitoring programmes,
b)       description of the different categories of monitoring programmes,
c)        quantitative criteria for conducting monitoring programmes,
d)       suitable monitoring methods and criteria for their selection,
e)       information that has to be collected for the design of a monitoring programme,
f)         general requirements for monitoring programmes (e.g. detection limits, tolerated uncertainties),
g)       frequencies of measurements calculated using the ICRP Occupational Intakes of Radionuclides (OIR) series,
h)       individual monitoring in specific cases (intake of actinides, intake via a wound and intake through the intact skin),
i)         quality assurance, and
j)         documentation, reporting and record-keeping.
This document does not apply to
—     the monitoring of exposure to radon and its radioactive decay products,
—     detailed descriptions of measuring methods and techniques,
—     detailed procedures for in vivo measurements and in vitro analysis,
—     interpretation of measurements results in terms of dose,
—     biokinetic data and mathematical models for converting measured activities into absorbed dose, equivalent dose and effective dose,
—     the investigation of the causes or implications of an exposure or intake.

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ISO
ISO 20553:2025(Main)
Radiation protection — Monitoring of workers occupationally exposed to a risk of internal contamination with radioactive material

This document specifies the minimum requirements for the design of programmes to monitor workers exposed to the risk of internal contamination by radioactive material and establishes principles for the development of compatible goals and requirements for monitoring programmes. This document specifies the a) purposes of monitoring and monitoring programmes, b) description of the different categories of monitoring programmes, c) quantitative criteria for conducting monitoring programmes, d) suitable monitoring methods and criteria for their selection, e) information that has to be collected for the design of a monitoring programme, f) general requirements for monitoring programmes (e.g. detection limits, tolerated uncertainties), g) frequencies of measurements calculated using the ICRP Occupational Intakes of Radionuclides (OIR) series, h) individual monitoring in specific cases (intake of actinides, intake via a wound and intake through the intact skin), i) quality assurance, and j) documentation, reporting and record-keeping. This document does not apply to — the monitoring of exposure to radon and its radioactive decay products, — detailed descriptions of measuring methods and techniques, — detailed procedures for in vivo measurements and in vitro analysis, — interpretation of measurements results in terms of dose, — biokinetic data and mathematical models for converting measured activities into absorbed dose, equivalent dose and effective dose, — the investigation of the causes or implications of an exposure or intake.

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IEC
IEC TR 63424-1:2024(Main)
Validation of dynamic power control and exposure time-averaging algorithms - Part 1: Cellular network implementations for SAR at frequencies up to 6 GHz

IEC TR 63424-1:2024 describes the methods for validating dynamic power control and (dynamic) exposure time-averaging (DPC-ETA) algorithms used in RF modem chipsets of wireless devices. The DPC-ETA implementations are exposure-based, where SAR is time-averaged according to power recorded by the RF modem. Time-averaging windows up to six minutes consistent with applicable SAR limits and regulatory policies are considered for frequencies up to 6 GHz. The DPC-ETA power control parameters are established based on SAR compliance results with all relevant design and operating tolerances taken into consideration. The device output power is controlled by DPC-ETA to maintain SAR compliance in real-time. While SAR compliance is evaluated independently by applying IEC/IEEE 62209-1528:2020 [1] , this document contains information for algorithm validation.
Quasi-static and dynamic power control test sequences are described in this document for algorithm validation. The test sequences are sent from a radio communication tester (RCT) and DPC-ETA responses are measured with conducted and radiated power measurement methods to confirm algorithm functionality. Test sequences for wireless configurations that need validation, including wireless mode transitions, call drop, handover, discontinuous transmission, and simultaneous transmission are described. Considerations for measurement automation to acquire time-aligned results for correlation with power changes in the test sequences are provided. DPC-ETA algorithms are validated by correlating the normalized power measurement results with the expected behaviours of an implementation for the applied test sequences. The procedures in this document also support algorithm validation of modular transmitters using an appropriate test platform. Guidance for using SAR methods in place of radiated power measurements and capacitive proximity sensor triggering with time-averaged detection are also included.
NOTE 1 A separate document will be considered to validate DPC-ETA implementations above 6 GHz, according to near-field millimetre-wave band power density exposure requirements. Substantially shorter time-averaging window durations, on the order of a few seconds, can be required to satisfy some national regulatory requirements.
NOTE 2 The scope of this document is limited to cellular network technologies that have RF modem transmission power dictated by a base station and therefore can be tested using RCT test sequences. Cellular network technologies (also referred to as wireless wide area networks (WWAN)) include Global System for Mobile Communications (GSM), Universal Mobile Telecommunication System (UMTS), Long-Term Evolution (LTE) and 5G New Radio (NR), including other related 2G, 3G, 4G, and 5G specifications, respectively. A separate document will be considered for validating DPC-ETA implementations for wireless local area network (WLAN) technologies, such as those based on the IEEE 802.11 standards series. With WLAN technologies, the transmit power is dictated independently by the RF modem and can be specific to each power control implementation, requiring different testing approaches.
NOTE 3 The procedures in this document can also be considered for 3GPP [2] 5G NR FR1 bands above 6 GHz.
NOTE 4 This document does not address algorithm validation for simultaneous transmission configurations involving transmitters that are not controlled by DPC-ETA operations in the RF modem. These are evaluated according to regulatory requirements.

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SIST
SIST ISO 7503-2:2025(Main)
Measurement of radioactivity - Measurement and evaluation of surface contamination - Part 2: Test method using wipe-test samples
ISO 7503-2:2016

ISO 7503 (all parts) and ISO 8769 are addressed to the people responsible for measuring the radioactivity present on solid surfaces.
ISO 7503-2:2016 applies to the evaluation of contamination on surfaces in terms of activity per unit area by an indirect method of measurement.
ISO 7503-2:2016 is applicable to well-defined surfaces, such as those of equipment and facilities, containers of radioactive materials, sealed sources and buildings or land.
ISO 7503-2:2016 can be used for laboratory and equipment/installation control and for remediation and monitoring activities to comply with release criteria.
ISO 7503-2:2016 also refers to institutions/authorities controlling nuclear material transports or material/equipment clearance according to national legislation guideline values or international convention limits.
ISO 7503-2:2016 does not apply to contamination of the skin, clothing or loose material, such as gravel.
NOTE Direct evaluation of surface contamination from alpha-emitters, beta-emitters and photon emitters is dealt with in ISO 7503-1. The calibration of instruments for the evaluation of radioactive surface contaminations is dealt with in ISO 7503-3.

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SIST
SIST ISO 7503-1:2025(Main)
Measurement of radioactivity - Measurement and evaluation of surface contamination - Part 1: General principles
ISO 7503-1:2016

ISO 7503 (all parts) and ISO 8769 are addressed to the people responsible for determining the radioactivity present on solid surfaces. ISO 7503 is published in three parts and can be used jointly or separately according to needs.
ISO 7503-1:2016 relates to the assessment of surface contamination by direct and indirect measurements and the calibration of the associated instrumentation.
The standard applies to alpha-, beta- and photon emitters and is intended for use by hospitals, universities, police, or industrial establishments. The standard also can be used in the assessment of activity on trucks, containers, parcels, equipment and is applicable in any organization which handles radioactive materials. Generally, it is applicable to well defined flat surfaces where direct methods are applicable, however, it can also be used for surfaces which are not flat and where indirect wipe tests would be appropriate. These investigations may be carried out on containers, inaccessible areas, non-flat areas where wipe tests can be used. This part of ISO 7503 may be useful in emergency situations, i.e. in nuclear accidents where health physics professionals would be involved.
ISO 7503-1:2016 does not apply to the evaluation of contamination of the skin, of clothing and of loose material such as gravel.
NOTE The test method using wipe-test samples for the evaluation of radioactive surface contaminations is dealt with in ISO 7503-2. The calibration of instruments for the evaluation of radioactive surface contaminations is dealt with in ISO 7503-3.

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SIST
SIST ISO 3999:2025(Main)
Radiation protection - Apparatus for industrial gamma radiography - Specifications for performance, design and tests
ISO 3999:2004

ISO 3999:2004 specifies the performance, design and test requirements of apparatus for gamma radiography with portable, mobile and fixed exposure containers of the various categories defined in Clause 4.
It applies to apparatus designed to allow the controlled use of gamma radiation emitted by a sealed radioactive source for industrial radiography purposes, in order that persons will be safeguarded when the apparatus is used in conformity with the regulations in force regarding radiation protection.
It is emphasised, however, that so far as transport of apparatus and sealed radioactive source is concerned, compliance with ISO 3999:2004 is no substitute for satisfying the requirements of relevant international transport regulations (IAEA Regulations for the safe transport of radioactive materials: IAEA-STI-PUB 998, Safety Standards Series ST-1 and ST-2, and/or the relevant national transport regulations).
The operational use of apparatus for industrial gamma radiography is not covered by ISO 3999:2004. Users of this equipment shall comply with national regulations and codes of practice.

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