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
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.
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
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 languagesale 10% offe-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 languagesale 10% offe-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 languagesale 10% offe-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 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 languagesale 10% offe-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 languagesale 10% offe-Library read for1 day
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 languagesale 10% offe-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.
- 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 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
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 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 nuclear power plants with water cooled reactors and, in particular, to the design of components and civil structures against seismic events in order to meet the safety objectives. For other nuclear facilities the applicability of the document is checked in advance, before it might be applied correspondingly. Seismic isolation is not adressed in the series of ISO 4917. The following safety objectives are defined in order to ensure the protection of people and the environment against radiation risks: a) controlling reactivity; b) cooling fuel assemblies; c) confining radioactive substances; d) limiting radiation exposure.
- Standard17 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
This document describes methodologies for radioactivity characterization of very low-level waste (VLLW) generated from the operation or decommissioning of nuclear facilities. The purpose is to differentiate VLLW from low-level radioactive solid waste and waste below clearance levels. The aim is to effectively characterize and to demonstrate that it satisfies the criteria for VLLW. This document focuses specifically on characterization methods of radioactive solid waste. Clearance and exemption monitoring are not covered within this document. Additionally, the characterization of liquid and gaseous wastes is also excluded from this document.
- Standard20 pagesEnglish languagesale 15% off
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.
- Standard29 pagesEnglish languagesale 15% off
- Standard34 pagesFrench languagesale 15% off
IEC TR 63415:2023 provides an overview over the formalized modelling and designing of cybersecure architectures to apply for I&C system cybersecurity enforcement at NPPs. The plant-specific risk assessment can use the techniques covered by this TR. This document considers the complex problem of NPP I&C architecture synthesis to address particular issues:
- asset classification,
- barrier measures assignment,
- the information transfer and links conformity with security requirements.
This document provides guidance on creating a comprehensive security model applicable to NPP I&C systems that describes NPP I&C cybersecurity architecture and aids in accomplishing the main tasks of I&C system secure design, which are:
- specification of system designs with increased determinism that enhance security,
- mapping of the security requirements into the security architecture of the I&C system,
- definition of the security requirements for information exchange between components within the I&C system, operators and other systems,
- assistance in the determination of the security degree assignment with a model-based technique considering asset properties and formal grouping of the assets,
design and establishment of security zones boundaries.
- Technical report56 pagesEnglish languagesale 15% off
IEC TR 63468:2023 overviews the fundamentals of artificial intelligence (AI) as it could potentially be applied within nuclear facilities and identifies proven or potential applications, with the objective to foster better understanding and adoption of AI technologies within such facilities. With the objective of supporting future standard development work of IEC SC 45A in this technical area, this document takes the initiative to propose a structure for SC 45A standard series on nuclear AI applications and recommends setting up a new dedicated working group to be responsible for and coordinate standard development efforts in this particular area, taking into account its cross-cutting nature.
- Technical report44 pagesEnglish languagesale 15% off
This document specifies the methods and techniques for leak tightness assessment of a metallic component at high temperature by measuring its total leakage rates in a vacuum chamber with a tracer gas leak detector and high-pressure helium gas or the gas mixture flowing out of the component as tracer gas during its thermal and pressure cycles at its operating conditions. The minimum detectable leakage rate can be as low as 10-10 Pa·m3/s, depending on the dimension, external configuration complexity and materials of the component, and is strongly related to the test system and the test conditions. This document is applicable for the hot helium leak test of in-vessel components as per its normal operating conditions in nuclear fusion reactors, which operate at elevated temperatures in an ultra-high vacuum environment down to 10-6 Pa and with inner flowing-coolant at operating pressure. It is also applicable to the overall leak tightness test of welds in other metallic components and equipment that could be evacuated and pressurized, such as pressurized tanks, pipes and valves in power plants, aerospace and other nuclear reactors.
- Standard12 pagesEnglish languagesale 15% off
This document is the first of a series of seven documents which outlines the general principles to manage the various type of radioactive waste, and provides guidance for the practical implementation of those principles. The purpose of this document is to address the following: a) principles, objectives and practical approaches for radioactive waste management; b) outline of the structure of series from ISO 24389-1 through ISO 24389-7.
- Standard15 pagesEnglish languagesale 15% off
- Standard15 pagesEnglish languagesale 15% off
This document specifies minimum nuclear criticality safety training requirements for operations staff, operations supervisors, and management.
This document is applicable to areas, processes or facilities containing quantities of fissile material for which nuclear criticality safety assessment is required as defined in ISO 1709.
This document is not applicable to the transport of fissile materials outside the boundaries of nuclear establishments.
- Standard16 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies minimum nuclear criticality safety training requirements for operations staff, operations supervisors, and management.
This document is applicable to areas, processes or facilities containing quantities of fissile material for which nuclear criticality safety assessment is required as defined in ISO 1709.
This document is not applicable to the transport of fissile materials outside the boundaries of nuclear establishments.
- Standard16 pagesEnglish languagesale 10% offe-Library read for1 day
The scope of ISO 16659 series is to provide different test methods aiming at assessing the efficiency of radioactive iodine traps in ventilation systems of nuclear facilities. The ISO 16659 series deals with iodine traps containing a solid sorbent — mainly activated and impregnated charcoal, the most common solid iodine sorbents used in the ventilation systems of nuclear facilities — as well as other sorbents for special conditions (e.g. high temperature zeolites). The scope of this document is to provide general and common requirements for the different test methods for industrial nuclear facilities. The different methods will be described in other specific parts of ISO 16659 series. Nuclear medicine applications are excluded from the scope of ISO 16659 series. In principle, ISO 16659 series is used mainly for filtering radioactive iodine, but other radioactive gases can also be trapped together with iodine. In such a case, some specificity may have to be adapted for these other radioactive gases in specific parts of ISO 16659 series. This document describes the main general requirements in order to check in situ the efficiency of the iodine traps, according to test conditions that are proposed to be as reproducible as possible.
- Standard21 pagesEnglish languagesale 15% off
- Standard24 pagesFrench languagesale 15% off
IEC 60951-1:2022 provides general guidance on the design principles and performance criteria for equipment to measure radiation and fluid (gaseous effluents or liquids) radioactivity levels at nuclear facilities during and after design basis accidents (DBA) and design extension conditions (DEC), including severe accident (SA). This document is limited to equipment for continuous monitoring of radioactivity in design basis accidents (DBA), design extension conditions (DEC), including severe accident (SA) and post-accident conditions. The purpose of this document is to lay down general requirements and give examples of acceptable methods for equipment for continuous monitoring of radioactivity within the facility during and after design basis accidents (DBA), design extension conditions (DEC), including severe accident (SA) in nuclear facilities. This third edition cancels and replaces the second edition published in 2009.The main technical changes with regard to the previous edition are as follows.
- title modified.
- to be consistent with the categorization of the accident condition.
- to update the references to new standards published since the second edition.
- to update the terms and definitions.
- Standard147 pagesEnglish languagesale 15% off
- Standard97 pagesEnglish and French languagesale 15% off
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.
- Standard79 pagesEnglish and French languagesale 15% off
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.
- Standard78 pagesEnglish languagesale 15% off
- Standard52 pagesEnglish and French languagesale 15% off
IEC 60910:2022 provides requirements for primary and secondary containment parameter monitoring that enable the operator to identify developing deviations from normal operation. The operator can then take corrective action at an early stage to prevent a minor failure from developing into a serious plant failure or an accident condition. This document is directed towards monitoring the primary and secondary containment under normal conditions only.
This second edition cancels and replaces the first edition, published in 1988. This edition includes the following significant technical changes with respect to the previous edition:
a. Modification of title;
b. Integration of new technology and knowledge;
c. Drafting directed towards monitoring conditions in containment under normal conditions.
- Standard32 pagesEnglish and French languagesale 15% off
IEC 60951-3:2022 provides general guidance on the design principles and performance criteria for equipment for continuous high range area gamma monitoring in nuclear facilities for accident and post-accident conditions. This document categorizes accident conditions into design basis accidents (DBA) and design extension conditions (DEC), including severe accident (SA). The purpose of this document is to lay down general requirements for equipment for continuous high range area gamma monitoring of radiation within the facility during and after accident conditions in nuclear facilities. This document is applicable to installed dose rate meters that are used to monitor high levels of gamma radiation during and after an accident. This third edition cancels and replaces the second edition published in 2009.The main technical changes with regard to the previous edition are as follows:
- Title modified.
- To be consistent with the categorization of the accident condition.
- To update the references to new standards published since the second edition.
- To update the terms and definitions.
This standard is to be read in conjunction with IEC 60951-1.
- Standard53 pagesEnglish languagesale 15% off
- Standard35 pagesEnglish and French languagesale 15% off
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).
- Standard18 pagesEnglish languagesale 15% off
- Standard19 pagesFrench languagesale 15% off
IEC/IEEE 62582-2:2022 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. This document is intended for application 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 2011, and its Amendment 1:2016. This edition includes the following significant technical changes with respect to the previous edition:
- Modification of the title;
- Consideration of publication of IEC/IEEE 60780-323.
- Standard70 pagesEnglish languagesale 15% off
- Standard46 pagesEnglish and French languagesale 15% off
IEC/IEEE 62582-4:2022 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. This second edition cancels and replaces the first edition published in 2011, and its Amendment 1:2016. This edition includes the following significant technical changes with respect to the previous edition:
- Consideration of publication of IEC/IEEE 60780-323;
- An example added in Annex B and update;
- Annex C added.
- Standard92 pagesEnglish languagesale 15% off
- Standard60 pagesEnglish and French languagesale 15% off
This document specifies requirements for the software of computer-based instrumentation and control (I&C) systems performing functions of safety category B or C as defined by IEC 61226. It complements IEC 60880 which provides requirements for the software of computer-based I&C systems performing functions of safety category A. It is consistent with, and complementary to, IEC 61513. Activities that are mainly system level activities (for example, integration, validation and installation) are not addressed exhaustively by this document: requirements that are not specific to software are deferred to IEC 61513. The link between functions categories and system classes is given in IEC 61513. Since a given safety-classified I&C system may perform functions of different safety categories and even non safety-classified functions, the requirements of this document are attached to the safety class of the I&C system (class 2 or class 3). This document is not intended to be used as a general-purpose software engineering guide. It applies to the software of I&C systems of safety classes 2 or 3 for new nuclear power plants as well as to I&C upgrading or back-fitting of existing plants. For existing plants, only a subset of requirements is applicable and this subset has to be identified at the beginning of any project. The purpose of the guidance provided by this document is to reduce, as far as possible, the potential for latent software faults to cause system failures, either due to single software failures or multiple software failures (i.e. Common Cause Failures due to software). This document does not explicitly address how to protect software against those threats arising from malicious attacks, i.e. cybersecurity, for computer-based systems. IEC 62645 provides requirements for security programmes for computer-based systems.
- Standard55 pagesEnglish languagesale 10% offe-Library read for1 day
See the scope of IEC 62988:2018. Adoption of IEC 62988:2018 is to be done without modification.
- Standard21 pagesEnglish languagesale 10% offe-Library read for1 day
See the scope of IEC 62988:2018. Adoption of IEC 62988:2018 is to be done without modification.
- Standard21 pagesEnglish languagesale 10% offe-Library read for1 day
This document presents the methods and provisions for sampling tritium and carbon‑14 in the gaseous effluents generated by nuclear facilities during operation and decommissioning. Specifically included are sample withdrawal location, extraction, transport flow measurement, and collection for later analysis. This document doesn’t address to real time measurements of tritium activity and carbon-14 activity in the effluent air of stacks and ducts. Information about real time measurements can be found in ISO 2889:2021, Annex H. Sample processing, analysis and calculations of tritium and carbon‑14 emissions will be addressed in future parts of ISO 20041.
- Standard37 pagesEnglish languagesale 15% off
- Standard39 pagesFrench languagesale 15% off
IEC 60964:2018 is available as IEC 60964:2018 RLV which contains the International Standard and its Redline version, showing all changes of the technical content compared to the previous edition.IEC 60964:2018 establishes requirements for the human-machine interface in the main control rooms of nuclear power plants. The document also establishes requirements for the selection of functions, design consideration and organization of the human-machine interface and procedures which are used systematically to verify and validate the functional design. These requirements reflect the application of human factors engineering principles as they apply to the human-machine interface during plant operational states and accident conditions (including design basis and design extension conditions), as defined in IAEA SSR-2/1 and IAEA NP-T-3.16. This third edition cancels and replaces the second edition published in 2009. This edition constitutes a technical revision. This edition includes the following significant technical changes with respect to the previous edition: a) to review the usage of the term “task” ensuring consistency between IEC 60964 and IEC 61839; b) to clarify the role, functional capability, robustness and integrity of supporting services for the MCR to promote its continued use at the time of a severe accident or extreme external hazard; c) to review the relevance of the standard to the IAEA safety guides and IEC SC 45A standards that have been published since IEC 60964:2009 was developed; d) to clarify the role and meaning of “task analysis”, e) to further delineate the relationships with derivative standards (i.e. IEC 61227, IEC 61771, IEC 61772, IEC 61839, IEC 62241 and others of relevance to the control room design); f) to consider its alignment with the Human Factors Engineering principles, specifically with the ones of IAEA safety guide on Human Factors (DS-492) to be issued.
- Standard46 pagesEnglish languagesale 10% offe-Library read for1 day
See the scope of IEC 62646:2016. Adoption of IEC 62646 is to be done without modification
- Standard48 pagesEnglish languagesale 10% offe-Library read for1 day
See the scope of the revised IEC 60709 in 45A/1113/CDV that was unchanged for the preparation of the proposal of FDIS to be circulated in parallel in CENELEC.
- Standard50 pagesEnglish languagesale 10% offe-Library read for1 day