27.120.20 - Nuclear power plants. Safety
ICS 27.120.20 Details
Nuclear power plants. Safety
Kernkraftwerke. Sicherheitsaspekte der Kerntechnik
Centrales nucléaires. Sécurité
Jedrske elektrarne. Varnost
General Information
Frequently Asked Questions
ICS 27.120.20 is a classification code in the International Classification for Standards (ICS) system. It covers "Nuclear power plants. Safety". 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 396 standards classified under ICS 27.120.20 (Nuclear power plants. Safety). 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.
e-Library Subscription
Create subscription and get permanent access to documents within 27.120.20 - Nuclear power plants. Safety
Currently subscription includes documents marked with .We are working on making all documents available within the subscription.
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.
- Standard42 pagesEnglish languagee-Library read for1 day
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.
- Standard42 pagesEnglish languagee-Library read for1 day
This document specifies the methods and the requirements for the supersonic molecular beam injection (SMBI) fuelling technique used in experimental magnetic confinement fusion facilities. It outlines the SMBI system components, specific requirements, and inspection procedures to ensure the effective and controlled injection of plasma fuel into fusion devices such as international thermonuclear experimental reactor and demonstration power plant. This document applies to the formation of supersonic molecular beam (SMB) and usage of the SMBI technique on the fusion devices, including the specification of gas pressure adjustment, beam characteristics and injection rate requirements, as well as the procedures for verifying these parameters.
- Standard13 pagesEnglish languagesale 15% off
This document specifies the performance and the functional characteristics of the low voltage static uninterruptible power supply (SUPS) systems in a nuclear power plant (NPP) and, when applicable, in nuclear facilities in general. An uninterruptible power supply (UPS) is an electrical equipment which draws electrical energy from a source, stores it, and maintains the supply in a specified form by means inside the equipment to output terminals. A SUPS has no rotating parts to perform its functions.
The specific design requirements for the components of the power supply system are covered by IEC standards and other standards listed in the normative references. Otherwise, specific component-level design requirements are outside the scope of this document.
- Standard41 pagesEnglish languagee-Library read for1 day
See the scope of IEC 61225:2025. Adoption is to be implemented without modification.
- Standard41 pagesEnglish languagee-Library read for1 day
This part of IEC/IEEE 62582 contains methods for condition monitoring of organic and polymeric materials in instrumentation and control systems using the indenter measurement technique in the detail necessary to produce accurate and reproducible measurements. It includes the requirements for the selection of samples, the measurement system and measurement conditions, and the reporting of the measurement results.
The different parts of IEC/IEEE 62582 are measurement standards, primarily for use in the management of ageing in initial qualification and after installation. IEC/IEEE 62582-1 includes requirements for the application of the other parts of the IEC/IEEE 62582 series and some elements which are common to all methods. Information on the role of condition monitoring in the qualification of equipment important to safety is found in IEC/IEEE 60780-323.
This document is intended for application to non-energised equipment.
- Standard24 pagesEnglish languagee-Library read for1 day
IEC 62705:2022 gives requirements for the lifecycle management of radiation monitoring systems (RMS) and gives guidance on the application of existing IEC standards covering the design and qualification of systems and equipment. The purpose of this document is to lay down requirements for the lifecycle management of RMSs and give application guidance. This document is intended to be consistent with the latest versions of International Standards dealing with radiation monitors, sampling of radioactive materials, instruments calibration, hardware and software design, classification, and qualification. This document is applicable to RMSs installed in nuclear facilities intended for use during normal operation, anticipated operational occurrences (AOO), design basis accidents (DBA) and design extension conditions (DEC), including severe accidents (SA). This second edition cancels and replaces the first edition published in 2014. This edition includes the following significant technical changes with respect to the previous edition:
- modification of the title.
- to be consistent with the categorization of the accident condition.
- to update the references to new standards published since the first edition.
- to update the terms and definitions.
- Standard29 pagesEnglish languagee-Library read for1 day
This part of IEC/IEEE 62582 contains methods for condition monitoring of organic and polymeric materials in instrumentation and control systems using tensile elongation techniques in the detail necessary to produce accurate and reproducible measurements. This document includes the requirements for selection of samples, the measurement system and conditions, and the reporting of the measurement results.
The different parts of IEC/IEEE 62582 are measurement standards, primarily for use in the management of ageing in initial qualification and after installation. IEC/IEEE 62582-1 includes requirements for the application of the other parts of IEC/IEEE 62582 and some elements which are common to all methods. Information on the role of condition monitoring in qualification of equipment important to safety is found in IEC/IEEE 60780-323.
This document is applicable to non-energised equipment.
- Standard27 pagesEnglish languagee-Library read for1 day
This part of the IEC/IEEE 62582 series contains requirements for application of the other parts of IEC/IEEE 62582 related to specific methods for condition monitoring in electrical equipment important to safety of nuclear power plants. It also includes requirements which are common to all methods. The procedures defined in IEC/IEEE 62582 are intended for detailed condition monitoring.
IEC/IEEE 62582 specifies condition monitoring methods in sufficient detail to enhance the accuracy and repeatability, and provide standard formats for reporting the results. The methods specified are applicable to electrical equipment containing polymeric materials. Some methods are especially designed for the measurement of condition of a limited range of equipment whilst others can be applied to all types of equipment for which the polymeric parts are accessible.
Although the scope of IEC/IEEE 62582 is limited to the application of instrumentation and control systems important to safety, the condition monitoring methods can also be applicable to other components which include polymeric materials.
The different parts of IEC/IEEE 62582 are measurement standards, primarily for use in the management of ageing in initial qualification and after installation. For the technical background of condition monitoring methods, reference is made to other IEC standards, e.g. IEC 60544-5 [1]. Information on the role of condition monitoring in qualification of electrical equipment important to safety is found in IEC/IEEE 60780-323. General information on management of ageing can be found in IEC 62342 [5] and IEEE 1205 [6].
NOTE A simplified version of the procedures can be appropriate for preliminary assessment of the need for detailed measurements.
- Standard24 pagesEnglish languagee-Library read for1 day
This part of IEC/IEEE 62582 specifies methods for condition monitoring of organic and polymeric materials in instrumentation and control systems using oxidation induction techniques in the detail necessary to produce accurate and reproducible measurements. It includes the requirements for sample preparation, the measurement system and conditions, and the reporting of the measurement results.
The different parts of IEC/IEEE 62582 are measurement standards, primarily for use in the management of ageing in initial qualification and after installation. IEC/IEEE 62582-1 includes requirements for the application of the other parts of the IEC/IEEE 62582 series and some elements which are common to all methods. Information on the role of condition monitoring in the qualification of equipment important to safety is found in IEC/IEEE 60780-323.
- Standard31 pagesEnglish languagee-Library read for1 day
IEC 62397:2022 describes the requirements for resistance temperature detectors (RTDs) suitable for applications in I&C systems important to safety of nuclear power plants. The requirements of RTDs include design, materials, manufacturing, testing, calibration, procurement, and inspection. RTDs used for safety applications in Nuclear Power Plants can be categorized into direct-immersed and thermowell-mounted RTDs.
This standard describes the requirements for the design, material selection, procurement, construction, and testing of resistance temperature detectors (RTDs) used in nuclear power plants (NPPs). These RTDs may be used in both the nuclear safety I&C systems and/or in the non-safety-related instrumentation systems.
This second edition cancels and replaces the first edition, published in 2007; it also cancels and replaces the first edition of IEC 61224:1993. This edition includes the following significant technical changes with respect to the previous edition.
- Standard42 pagesEnglish languagee-Library read for1 day
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]).
- Standard39 pagesEnglish languagesale 15% off
- Standard41 pagesFrench languagesale 15% off
IEC 61513:2026 provides requirements and recommendations for the overall I&C which may contain one or several of these technologies.
This document highlights also the need for complete and precise requirements, derived from the plant safety goals, as a pre-requisite for generating the comprehensive requirements for the overall I&C, and hence for the individual I&C systems important to safety.
This document introduces the concept of a safety lifecycle for the overall I&C including the I&C architecture, and a safety lifecycle for the individual systems. By this, it highlights the relations between the safety objectives of the NPP and the requirements for the architecture of the I&C systems important to safety, and the relations between the I&C architecture and the requirements of the individual systems important to safety.
Standards such as ISO/IEC/IEEE 15288 provide an overarching concept of system life cycle provisions covering product-related processes as well business development. The scope of IEC 61513 refers to safety aspects and their demonstration and significantly deepens the considerations of ISO/IEC/IEEE 15288 in this field.
The lifecycles illustrated in and followed by this document are not the only ones possible; other lifecycles can be followed, provided that the requirements stated in this document are satisfied.
This document applies to the I&C of new nuclear power plants as well as to I&C upgrading or back-fitting of existing plants.
This third edition cancels and replaces the second edition, published in 2011. This edition includes the following significant technical changes with respect to the previous edition:
- to align this document with the recent IAEA documents SSR-2/1 and SSG-39,
- to review the existing requirements and to update the terminology and definitions;
- to take account of, as far as possible, requirements associated with standards published or thoroughly revised since the second edition, IEC 62566, IEC 61226, IEC 62138, IEC 60987, IEC 63046 and IEC 63351;
- to incorporate the technical requirements related to I&C systems and equipment from IEC 61226:2020, Annex A.
- Standard120 pagesEnglish languagesale 15% off
See the scope of IEC/IEEE 62582-2:2022. Adoption is to be implemented without modification.
- Standard24 pagesEnglish languagee-Library read for1 day
See the scope of IEC/IEEE 62582-4:2022. Adoption is to be implemented without modification.
- Standard31 pagesEnglish languagee-Library read for1 day
IEC 62397:2022 describes the requirements for resistance temperature detectors (RTDs) suitable for applications in I&C systems important to safety of nuclear power plants. The requirements of RTDs include design, materials, manufacturing, testing, calibration, procurement, and inspection. RTDs used for safety applications in Nuclear Power Plants can be categorized into direct-immersed and thermowell-mounted RTDs. This standard describes the requirements for the design, material selection, procurement, construction, and testing of resistance temperature detectors (RTDs) used in nuclear power plants (NPPs). These RTDs may be used in both the nuclear safety I&C systems and/or in the non-safety-related instrumentation systems. This second edition cancels and replaces the first edition, published in 2007; it also cancels and replaces the first edition of IEC 61224:1993. This edition includes the following significant technical changes with respect to the previous edition.
- Standard42 pagesEnglish languagee-Library read for1 day
See the scope of IEC/IEEE 62582-1:2024. Adoption is to be implemented without modification.
- Standard24 pagesEnglish languagee-Library read for1 day
See the scope of IEC/IEEE 62582-3:2024. Adoption is to be implemented without modification.
- Standard27 pagesEnglish languagee-Library read for1 day
IEC 62705:2022 gives requirements for the lifecycle management of radiation monitoring systems (RMS) and gives guidance on the application of existing IEC standards covering the design and qualification of systems and equipment. The purpose of this document is to lay down requirements for the lifecycle management of RMSs and give application guidance. This document is intended to be consistent with the latest versions of International Standards dealing with radiation monitors, sampling of radioactive materials, instruments calibration, hardware and software design, classification, and qualification. This document is applicable to RMSs installed in nuclear facilities intended for use during normal operation, anticipated operational occurrences (AOO), design basis accidents (DBA) and design extension conditions (DEC), including severe accidents (SA). This second edition cancels and replaces the first edition published in 2014. This edition includes the following significant technical changes with respect to the previous edition: - modification of the title. - to be consistent with the categorization of the accident condition. - to update the references to new standards published since the first edition. - to update the terms and definitions.
- Standard29 pagesEnglish languagee-Library read for1 day
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).
- Standard17 pagesEnglish languagesale 15% off
- Standard17 pagesFrench languagesale 15% off
This part of IEC 62676 specifies the functions, performance, interfaces, environmental adaptability, test methods, performance evaluation and grading rules of real-time intelligent video analysis in surveillance systems.
This document applies to live and forensic, real-time intelligent video analysis devices and systems in video surveillance.
The document is centred on testing performance and grading device functionality which enables:
• Core capability: Classification of objects, detection of specific "object activity", such as "stopping", "starting", "direction of movement", etc.
Examples are listed in Annex A.
• Complex capability: Detection of "scenarios" which are based on combinations of object activity, such as "loitering", "perimeter intrusion detection", "person down", "tailgating", "intrusion", "abandoned object detection", explosion, fire, flood, potential terrorist attack using a vehicle, owner of an abandoned bag, etc.
Examples of current scenarios are listed and described in Annex B.
• Degree of difficulty: The application of real operating environments to test the performance under known or required operating stress levels, examples of operating stress levels that are sterile or non-sterile, indoor or outdoor, target obscuration levels, extreme weather conditions, vibrating mechanical rugged environments causing image shake resulting in degradation of image quality requirement, see Table 1 and Annex C.
The purpose of this document is to provide end users, at different levels of the service process, from users and installers, integrators and maintenance companies, to certification providers, with methods to measure the performance of video analysis systems that must also comply with other parts of the standard.
- Standard228 pagesEnglish languagee-Library read for1 day
This Standard specifies the functions, performance, interfaces, environmental adaptability, test methods, performance evaluation and grading rules of real-time intelligent video analysis in surveillance systems. This Standard applies to live and forensic, real-time intelligent video analysis devices and systems in video surveillance. The standard is centered on testing performance and grading device functionality which enables; - Core Capability: Classification of Objects, Detection of specific "object activity" such as "stopping", "starting", "direction of movement", etc. Examples and current expanded list in Annex H - Complex Capability: Detection of "scenarios" which are based on combinations of object activity such as "loitering", "perimeter intrusion detection", "person down", "tailgating", "intrusion", “abandoned object detection”, Explosion, Fire, Flood, Potential Terrorist attack using a vehicle, Owner of an abandoned bag, etc. Examples of current scenarios are listed and described in Annex I
- Standard228 pagesEnglish languagee-Library read for1 day
IEC 63413:2026 provides guidance and establishes requirements for the qualification of I&C platforms, according to IEC nuclear standards, aimed to be used in nuclear applications important to safety. Qualification of an I&C platform (also called pre-qualification or generic qualification) is performed as a generic activity outside the framework of a plant-specific application project. Platform qualification aims to fulfil in an anticipated manner all requirements leading to an I&C platform fully suitable for the implementation of a plant-specific application project.
The platform qualification covers consequently all I&C platform specific aspects including hardware, software, HPD, engineering tools, environmental qualification, quality and the applied safety life cycle supporting these activities. Platform qualification also considers interaction of platform assemblies. This document applies to I&C platforms under development, as well as to pre-existing I&C platforms.
This document provides guidance on what is relevant to I&C platform qualification and what is relevant to the implementation of an I&C system design based on a qualified I&C platform.
The objective of this document is to identify those requirements that relate closely to an I&C platform qualification and aims to support a two-step approach for the licensing of I&C systems based on this I&C platform. If the complete qualification of an I&C system is performed in the framework of a plant-specific application, this document does not apply.
- Standard46 pagesFrench languagesale 15% off
- Standard86 pagesEnglish and French languagesale 15% off
IEC 63423:2026 applies to cable connector assemblies for harsh environment purposes that are important to safety. It covers the engineering safety aspects to be met in the design, qualification, fabrication, assembling, testing, and installation on site of cable connector assemblies to be operated under accident conditions.
This document can be additionally used for cable assemblies that are operated under normal conditions.
This document covers cable connector assemblies that are used for the following generic functions:
- signal transmission (AC or DC voltage/current; pulses, frequency), or
- supplying electrical energy to sensors, transducers, or other devices.
- Standard33 pagesEnglish languagesale 15% off
- Standard36 pagesFrench languagesale 15% off
IEC 62676-6:2026 specifies the functions, performance, interfaces, environmental adaptability, test methods, performance evaluation and grading rules of real-time intelligent video analysis in surveillance systems.
This document applies to live and forensic, real-time intelligent video analysis devices and systems in video surveillance.
The document is centred on testing performance and grading device functionality which enables:
• Core capability: Classification of objects, detection of specific "object activity", such as "stopping", "starting", "direction of movement", etc.
Examples are listed in Annex A.
• Complex capability: Detection of "scenarios" which are based on combinations of object activity, such as "loitering", "perimeter intrusion detection", "person down", "tailgating", "intrusion", "abandoned object detection", explosion, fire, flood, potential terrorist attack using a vehicle, owner of an abandoned bag, etc.
Examples of current scenarios are listed and described in Annex B.
• Degree of difficulty: The application of real operating environments to test the performance under known or required operating stress levels, examples of operating stress levels that are sterile or non-sterile, indoor or outdoor, target obscuration levels, extreme weather conditions, vibrating mechanical rugged environments causing image shake resulting in degradation of image quality requirement, see Table 1 and Annex C.
The purpose of this document is to provide end users, at different levels of the service process, from users and installers, integrators and maintenance companies, to certification providers, with methods to measure the performance of video analysis systems that must also comply with other parts of the standard.
- Standard224 pagesEnglish languagesale 15% off
- Standard236 pagesFrench languagesale 15% off
- Standard460 pagesEnglish and French languagesale 15% off
IEC TR 63400:2025 augments that description to enable users of individual IEC SC 45A standards to obtain a more comprehensive understanding of the overall structure of the series and its relationship with other standards bodies and standards. The publication of this document and its subsequent editions should also enable minor changes in the structure to be described without the need for amending the common description that is included in the Introduction, item d), of all IEC SC 45A documents.
- Technical report69 pagesEnglish languagesale 15% off
- Technical report144 pagesEnglish languagesale 15% off
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.
- Standard89 pagesEnglish languagee-Library read for1 day
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.
- Standard37 pagesEnglish languagee-Library read for1 day
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).
- Standard27 pagesEnglish languagee-Library read for1 day
IEC 63374:2025 specifies the characteristics and test methods for reactivity meters. Other methods for measuring reactivity are not addressed in this document. This document provides guidance for the design, production and operation of reactivity meters. This document is applicable to various types of nuclear reactors that can be described by the neutron kinetic point reactor model, such as pressurized water reactors (PWRs), boiling-water reactors (BWRs) or fast breeder reactors (FBRs). This document is applicable to all on-line measuring instruments that directly obtain reactivity values by measuring the neutron flux. The subject relates to the reactor nuclear parameter measurement domain.
- Standard18 pagesEnglish languagesale 15% off
- Standard19 pagesFrench languagesale 15% off
- Standard37 pagesEnglish and French languagesale 15% off
IEC 63435:2025 specifies the characteristics of operator support systems (OSS) used by the control room staff, maintenance engineers and emergency response staff, establishes general principles for OSS lifecycle and requirements for OSS design following the human factors engineering (HFE) programme. This document also gives the human factors guidelines and the verification and validation (V&V) requirements for OSS design.
This document is applicable to new nuclear facilities whose conceptual design is initiated after the publication of this document but it can also be used for designing OSS in existing nuclear facilities.
- Standard33 pagesEnglish languagesale 15% off
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).
- Standard89 pagesEnglish languagee-Library read for1 day
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.
- Standard37 pagesEnglish languagee-Library read for1 day
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).
- Standard27 pagesEnglish languagee-Library read for1 day
The objective of this document is to characterize the gaseous effluents tritium and carbon-14 generated by nuclear facilities during operation and decommissioning and occurring in the same chemical species as hydrogen and carbon, e. g. as water vapour (HTO), hydrogen gas (HT, TT), carbon dioxide (14CO2), carbon monoxide (14CO), methane (CH3T, 14CH4). It concerns measurements on samples that are representative of a certain volume stream or volume of discharge during a given period of time and of the corresponding volume discharged. The result is therefore expressed in becquerels. This document applies to samples that were obtained by sampling methods according to ISO 20041-1[ REF Reference_ref_10 \r \h 9 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310030000000 ] and describes — analysis methods for the determination of tritium and carbon-14 activities by liquid scintillation counting, and — calculation methods to determine the tritium activities discharged as tritiated water vapour (HTO) and tritium in other chemical compounds (non-HTO) as well as carbon-14 activities discharged as carbon dioxide (14CO2) and carbon-14 in other chemical compounds (non-14CO2). This document does not apply to tritium and carbon-14 activity concentrations in the environmental air, e.g. in the vicinity of nuclear installations. The accountability rules of the activities discharged necessary for the establishment of regulatory reports do not fall within the scope of this document and are the responsibility of the regulatory bodies.
- Standard41 pagesEnglish languagesale 15% off
- Standard43 pagesFrench languagesale 15% off
This standard specifies the general requirements of the corrosion control engineering life cycle in nuclear power plants. This standard applies to of various activities management of the corrosion control engineering life cycle in nuclear power plants.
- Standard12 pagesEnglish languagesale 15% off
IEC 61225:2025 specifies the performance and the functional characteristics of the low voltage static uninterruptible power supply (SUPS) systems in a nuclear power plant (NPP) and, when applicable, in nuclear facilities in general. An uninterruptible power supply (UPS) is an electrical equipment which draws electrical energy from a source, stores it, and maintains the supply in a specified form by means inside the equipment to output terminals. A SUPS has no rotating parts to perform its functions. The specific design requirements for the components of the power supply system are covered by IEC standards and other standards listed in the normative references. Otherwise, specific component-level design requirements are outside the scope of this document.
- Standard36 pagesEnglish languagesale 15% off
- Standard75 pagesEnglish languagesale 15% off
IEC 60911:2025 applies to pressurized water reactors (PWRs) and presents requirements for the monitoring of adequate cooling within the core in all operations, including normal and abnormal operations. Requirements for core cooling monitoring during conditions beyond a design basis accident, i.e. a design extension condition of type A or type B, are also covered in this document.
This document defines requirements for instrumentation to measure coolant parameters, which are of interest when abnormal conditions arise with either one or two phases of coolant or with gas included in the reactor pressure vessel (RPV).
This second edition cancels and replaces the first edition published in 1987. This edition includes the following significant technical changes with respect to the previous edition:
a) Modification of the title.
b) Integration and merging with the content of IEC 62117:1999 relative to the monitoring of core cooling during cold shutdown.
c) Integration of feedback following the 2011 Fukushima accident.
- Standard45 pagesEnglish languagesale 15% off
This document specifies the utilization and characteristics of instrumentation used to detect seismic events at nuclear power plants with water cooled reactors. The document can also be applied to other nuclear facilities after verifying its applicability. The following types of electrical systems and equipment are not covered by this document: — seismic instrumentation involved in the implementation of nuclear safety functions as defined by IEC 61226, for example automatic shutdown systems; — seismic instrumentation not involved in the implementation of nuclear safety functions as defined by IEC 61226 but which due, for example, to close proximity to other safety classified systems, requires hardware qualification to be performed. Such systems are specified, designed, manufactured, qualified, operated and dismantled according to the relevant requirements of IEC standards, in particular IEC 61513 and the lower level IEC standards according to the safety class and technologies used. Seismic instrumentation used for the implementation of seismic reactor trip systems are developed according to the requirements of IEC 63186. An automatic shutdown system is not covered by this document. This document specifies the requirements to be fulfilled by the seismic instrumentation such that, firstly, it can be ascertained whether any of the design quantities on which the plant walk-down level and the inspection levels are based have been exceeded and that, secondly, the recording of the time history of the earthquake provides the necessary input values for a post-seismic analysis. The requirements are specified such that, independent of the detection and recording system, comparable results within tolerances are achieved in the time range as well as the frequency range.
- Standard8 pagesEnglish languagesale 15% off
IEC/IEEE 63332-387:2024 defines the criteria for the application and testing of diesel generator (DG) units used as safety class standby power supplies in nuclear facilities. In general, the standard applies to new nuclear facilities as well as for upgrading or back-fitting of existing facilities. Existing facilities can voluntarily adopt the requirements to enhance the performance capabilities and reliability of the installed DG units. The standard can be used in applications where highly reliable onsite alternating current (AC) power source is required to maintain plant safety following an event with potential loss of offsite power for an extended duration.
This document provides the principal design criteria, the design features, testing, and qualification requirements for the individual DG units that enable them to meet their functional requirements as a part of the standby power supply under the conditions produced by the design basis events catalogued in the plant safety analysis.
- Standard139 pagesEnglish and French languagesale 15% off
IEC/IEEE 62582-1:2024 contains requirements for application of the other parts of IEC/IEEE 62582 related to specific methods for condition monitoring in electrical equipment important to safety of nuclear power plants. It also includes requirements which are common to all methods. The procedures defined in IEC/IEEE 62582 are intended for detailed condition monitoring.
IEC/IEEE 62582 specifies condition monitoring methods in sufficient detail to enhance the accuracy and repeatability, and provide standard formats for reporting the results. The methods specified are applicable to electrical equipment containing polymeric materials. Some methods are especially designed for the measurement of condition of a limited range of equipment whilst others can be applied to all types of equipment for which the polymeric parts are accessible.
- Standard21 pagesEnglish languagesale 15% off
- Standard21 pagesEnglish languagesale 15% off
- Standard44 pagesEnglish and French languagesale 15% off
IEC 63351:2024 specifies the basic principles and requirements for the application of a human factors engineering (HFE) programme to the design of the human-machine interfaces (HMI) throughout the lifetime of a nuclear facility. The focus of this document is on control rooms and control functions as discussed in the text.
This document focuses on the application of a human factors engineering (HFE) programme to the design of the human-machine interfaces throughout the lifetime of a nuclear facility, including consideration of plant modifications.
This document is applicable to nuclear facilities such as: nuclear power plants (NPPs), research reactors, uranium enrichment and nuclear fuel fabrication facilities, spent fuel storage and reprocessing facilities.
- Standard140 pagesEnglish and French languagesale 15% off
IEC TR 63486:2024 provides a cybersecurity framework for digital I&C programmable systems [2]. IEC 62645 [1] aligns strongly with the information security management system (ISMS) elements detailed within ISO/IEC 27001:2013 [2]. The ISO/IEC ISMS structure corresponds to the “I&C digital programmable system cybersecurity program” in the context (as defined in 5.2.1 of IEC 62645:2019 [1]).
The scope of this document is to capture the national and international cyber-risk approaches employed to manage cybersecurity risks associated with Instrumentation and Control (I&C) and Electrical Power Systems (EPS) at a Nuclear Power Plant (NPP).
This document summarizes an evaluation of cyber-risk approaches that are in use by nuclear facility operators to manage cybersecurity risks.
The scope of this document generally follows the exclusions of IEC 62645 which are:
- Non-malevolent actions and events such as accidental failures, human errors (except those stated above, such as impacting the performance of cybersecurity controls), and natural events. In particular, good practices for managing applications and data, including backup and restoration related to accidental failure, are out of scope.
This document summarizes key insights of the international and cyber-risk approaches used at NPPs regarding the application of ISO/IEC 27005:2018 [5]. The evaluation is based on 11 challenges to cybersecurity risk management and their applicability to NPP risk management. The challenges are detailed in Clause 7. This document also relates the risk management elements of IEC 62645 and IEC 63096.
- Technical report160 pagesEnglish languagesale 15% off
IEC 63272:2024 specifies the performance and functional characteristics of the on-site AC interruptible power supply systems and applies to new nuclear facilities and newly installed or upgraded on-site AC interruptible power supply systems.
The specific design requirements for the components of the power supply system are defined by the IEC standards listed in the normative references and are outside the scope of this document.
The purpose of this document is to provide high level requirements for the design of on-site AC interruptible power supply systems as part of the overall electrical distribution system in a nuclear facility. This document defines the requirements for an electrical designer to establish the design of the AC interruptible electrical power supply for nuclear facilities. It is used in conjunction with Level 1 standard IEC 63046.
- Standard116 pagesEnglish and French languagesale 15% off
IEC 63298:2024 provide high level requirements and recommendations for the coordination of NPPs and the electric grid; see also item a) of the Introduction. The specific design requirements for components and equipment are covered by other specific IEC standards outside the scope of this document. This document also defines the coordination requirements to ensure that operating instructions for the electric grid and the NPP are developed to provide a means of safe and reliable operation. This document also defines the requirements for the development of a framework for any specific tests that may be deemed necessary for the electric grid and the NPP, such as testing of NPP regulation capabilities and load rejection to house load operation tests.
- Standard50 pagesEnglish and French languagesale 15% off
IEC/IEEE 62582-3:2024 contains methods for condition monitoring of organic and polymeric materials in instrumentation and control systems using tensile elongation techniques in the detail necessary to produce accurate and reproducible measurements. This document includes the requirements for the selection of samples, the measurement system and conditions, and the reporting of the measurement results. The different parts of IEC/IEEE 62582 are measurement standards, primarily for use in the management of ageing in initial qualification and after installation. IEC/IEEE 62582-1 includes requirements for the application of the other parts of IEC/IEEE 62582 and some elements which are common to all methods. This document applies to non-energised equipment. This document is published as an IEC/IEEE Dual Logo standard. This second edition cancels and replaces the first edition published in 2012.
This edition includes the following technical changes with respect to the previous edition:
a) Updated best practices relating to condition monitoring using the tensile elongation method.
b) Updated bibliography, references and context.
- Standard79 pagesEnglish languagesale 15% off
- Standard51 pagesEnglish and French languagesale 15% off
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).
- Standard80 pagesEnglish languagesale 15% off
- Standard89 pagesFrench languagesale 15% off
This document applies to nuclear power plants with water cooled reactors. For other nuclear facilities check the applicability of the document in advance, before it might be applied correspondingly. This document specifies the requirements for the earthquake safety of components. The operation-specific safety-related requirements for each component, e.g. load-bearing capacity (stability), integrity and functionality (see 4.1) are not the subject of this document. With regard to analysing the mechanical behaviour of the individual components and verifying the fulfillment of their safety related functions, additionally, the respective component-specific standards need to be consulted. In this document, the term "mechanical components" refers to components such as vessels, heat exchangers, pumps, valves, lifting gear, distribution systems and pipe lines including their support structures in as far as these components are not considered to be civil structures in accordance with ISO 4917-3. Liners, crane runways, platforms and scaffoldings are not considered as being part of these mechanical components. In this document, the term electrical components refers to the combination of electrical devices including all electrical connections and their support structures (e.g. cabinets, frames, consoles, brackets, suspensions or supports). Supplementary to this document the seismic qualification of electrical components is reported in IEC/IEEE 60980-344. NOTE This document is independent of national standards. Recommendations, given in Annex A, are mainly based on the Eurocodes-Design-Philosophy and European Standards. Alternatively other equivalent standards or regulations can be used in case the general requirements given in this document together with Annex A can be met.
- Standard36 pagesEnglish languagesale 15% off
This document applies to nuclear power plants with water cooled reactors. This document does not apply to earthquakes stronger than the design basis earthquake. This document specifies guidance on the actions to be taken in preparation for and following an earthquake at a nuclear power plant. This document is intended to be used as a guideline for decision making regarding continued operation, shutdown and restart of the nuclear power plant after an earthquake. It can also be used to assist operating organizations in the preparation and implementation of an overall pre- and post-earthquake action programme for dealing with situations in accordance with the level of seismic ground motion experienced at the site, and the seismic design level of the plant.
- Standard12 pagesEnglish languagesale 15% off
This document applies to civil structures of nuclear power plants with water cooled reactors in order to achieve the safety objectives given in ISO 4917-1. For other nuclear facilities the applicability of the document needs to be checked in advance, before it might be applied correspondingly. This document specifies the requirements for civil structures for the verification of their load-bearing capacity in case of a seismic event. Additionally, requirements are specified pertaining to the verification of the serviceability of civil structures as far as necessary for maintaining their safety-related function in case of a seismic event (e.g. deformation and crack-width limitations). This document will be applied under the presumption that the geology and tectonics of the plant site have been investigated with special emphasis on the existence of active geological faults and lasting geological ground displacements, and that the site has been deemed suitable for a nuclear installation. To achieve these goals, this document deals with the requirements specific to the seismic design of civil structures above and beyond their conventional design. The basic requirements of these precautionary measures are dealt with in ISO 4917-1. This document does not apply to cranes, to detachment devices for lifting equipment nor to the supporting and mounting constructions of components. This document is independent of national standards. Recommendations, given in Annex A, are mainly based on the KTA Design-Philosophy and European standards. Alternatively other equivalent standards or regulations can be used in case the general requirements given in this document can be met. NOTE The term civil structures as used in this document comprise buildings and structural members made of reinforced concrete, pre-stressed concrete, steel, as well as steel composite structures and masonry. Among others, these include the containment, crane runways, platforms, fastening constructions and canals.
- Standard23 pagesEnglish languagesale 15% off