This International Standard describes methods for establishing seismic qualification procedures
that will yield quantitative data to demonstrate that the equipment can meet its performance
requirements. This document is applicable to electrical, mechanical, instrumentation and control
equipment/components that are used in nuclear facilities. This document provides methods and
documentation requirements for seismic qualification of equipment to verify the equipment’s
ability to perform its s...
view more

    • sale 10% off
    • Standard
      85 pages
      English language
    • e-Library read for
      1 day
    • sale 10% off
    • Draft
      85 pages
      English language
    • e-Library read for
      1 day

IEC/IEEE 60980-344:2020 describes methods for establishing seismic qualification procedures that will yield quantitative data to demonstrate that the equipment can meet its performance requirements. This document is applicable to electrical, mechanical, instrumentation and control equipment/components that are used in nuclear facilities. This document provides methods and documentation requirements for seismic qualification of equipment to verify the equipment’s ability to perform its specified ...view more

    • sale 15% off
    • Standard
      82 pages
      English language

IEC 61031:2020 applies to the design, location and application of installed equipment for monitoring local gamma radiation dose rates within nuclear facilities during normal operation and anticipated operational occurrences. High range area gamma radiation dose rate monitoring equipment for accident conditions currently addressed by IEC 60951-1 and IEC 60951-3 is not within the scope of this document. This document does not apply to the measurement of neutron dose rate. Additional equipment for ...view more

    • sale 15% off
    • Standard
      22 pages
      English language

This document gives guidelines for pre-service inspections (PSI) and in-service inspections (ISI) of the surfaces using the magnetic particle testing and penetrant testing on components of the reactor coolant circuit of light water reactors. This document is also applicable to other components of nuclear installations. Test systems for the localisation of surface inhomogeneities and requirements for test personnel, test devices, test media, accessories as well as optical auxiliaries, the prepara...view more

    • sale 15% off
    • Standard
      15 pages
      English language
    • sale 15% off
    • Draft
      15 pages
      English language

This document gives guidelines for pre-service-inspections (PSI) and in-service inspections (ISI) with mechanized ultrasonic test (UT) devices on components of the reactor coolant circuit of light water reactors. This document is also applicable on other components of nuclear installations. Mechanized ultrasonic inspections are carried out in order to enable an evaluation in case of — fault indications (e.g. on austenitic weld seams or complex geometry), — indications due to geometry (e.g. in ca...view more

    • sale 15% off
    • Standard
      33 pages
      English language
    • sale 15% off
    • Draft
      33 pages
      English language

This document gives guidelines for pre-service inspection (PSI) and in-service inspections (ISI) for reactor coolant circuit components of light water reactors and their installations as direct or remote visual testing in the form of a — general visual testing (overview), or — selective visual testing (specific properties). This document is also applicable to other components of nuclear installations. The requirements in this document focuses on remote (mechanized) visual testing, but also speci...view more

    • sale 15% off
    • Standard
      14 pages
      English language
    • sale 15% off
    • Draft
      14 pages
      English language

This document gives guidelines for in-service system pressure tests of the reactor coolant circuit of light water reactors. This document specifies the test technique, the requirements for measuring equipment and additional devices, the preparation and performance of the test as well as the recording and documentation, for the purpose to ensure the reliability and comparability of tests. NOTE Data on (test) pressure, (test) temperature, scope of testing, rates of change of pressure and temperatu...view more

    • sale 15% off
    • Standard
      8 pages
      English language
    • sale 15% off
    • Draft
      8 pages
      English language

This document gives guidelines for pre-service inspection (PSI) and in-service inspections (ISI) by eddy current tests on non-ferromagnetic steam generator heating tubes of light water reactors, whereby the test is carried out using mechanised test equipment outwards from the tube inner side. An in-service eddy current test of steam generator heating tube plugs as a component of the primary circuit is not an object of this document. Owing to the different embodiments of steam generator heating t...view more

    • sale 15% off
    • Standard
      19 pages
      English language
    • sale 15% off
    • Draft
      19 pages
      English language

ISO 19226:2017 provides a procedure for the evaluation of irradiation data in the region between the reactor core and the inside surface of the containment vessel, through the pressure vessel and the reactor cavity, between the ends of active fuel assemblies, given the neutron source in the core.
NOTE These irradiation data could be neutron fluence or displacements per atom (dpa), and Helium production.
The evaluation employs both neutron flux computations and measurement data from in-vessel a...
view more

    • sale 10% off
    • Standard
      20 pages
      English language
    • e-Library read for
      1 day

ISO 19226:2017 provides a procedure for the evaluation of irradiation data in the region between the reactor core and the inside surface of the containment vessel, through the pressure vessel and the reactor cavity, between the ends of active fuel assemblies, given the neutron source in the core.
NOTE These irradiation data could be neutron fluence or displacements per atom (dpa), and Helium production.
The evaluation employs both neutron flux computations and measurement data from in-vessel a...
view more

    • sale 10% off
    • Standard
      20 pages
      English language
    • e-Library read for
      1 day

This document specifies requirements for the unique identification of fuel assemblies utilized in nuclear power plants. It was developed primarily for commercial light-water reactor fuel, but can be used for any reactor fuel contained in discrete fuel assemblies that can be identified with an identification code as specified by this document. This document defines the characters and proposed sequence to be used in assigning identification to the fuel assemblies. The identification is intended to...view more

    • sale 15% off
    • Standard
      4 pages
      English language

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 syste...
view more

    • sale 15% off
    • Standard
      87 pages
      English and French language

ISO 18077:2018 applies to the reactor physics tests that are performed following a refuelling or other core alteration of a PWR for which nuclear design calculations are required. This document does not address the physics test program for the initial core of a commercial PWR[1]. ISO 18077:2018 specifies the minimum acceptable startup reactor physics test program to determine if the operating characteristics of the core are consistent with the design predictions, which provides assurance that th...view more

    • sale 15% off
    • Standard
      28 pages
      English language

ISO 18075:2018 provides guidance for performing and validating the sequence of steady-state calculations leading to prediction, in all types of operating UO2-fuel commercial nuclear reactors, of: - reaction-rate spatial distributions; - reactivity; - change of nuclide compositions with time. ISO 18075:2018 provides: a) guidance for the selection of computational methods; b) criteria for verification and validation of calculation methods used by reactor core analysts; c) criteria for evaluation o...view more

    • sale 15% off
    • Standard
      23 pages
      English language

ISO 18229:2018 defines the essential technical requirements that are addressed in the process of design and construction of Generation IV (GEN IV) nuclear reactors. It does not address operation, maintenance and in-service inspection of reactors. Six reactor concepts are considered for GEN IV: the sodium fast reactor, the lead fast reactor, the gas fast reactor, the very high temperature reactor, the supercritical water reactor and the molten salt reactor. Annex A details the main characteristic...view more

    • sale 15% off
    • Standard
      29 pages
      English language
    • sale 15% off
    • Standard
      30 pages
      French language

ISO 19226:2017 provides a procedure for the evaluation of irradiation data in the region between the reactor core and the inside surface of the containment vessel, through the pressure vessel and the reactor cavity, between the ends of active fuel assemblies, given the neutron source in the core. NOTE These irradiation data could be neutron fluence or displacements per atom (dpa), and Helium production. The evaluation employs both neutron flux computations and measurement data from in-vessel and...view more

    • sale 15% off
    • Standard
      12 pages
      English language
    • sale 15% off
    • Standard
      13 pages
      French language

IEC 62516-2:2011 specifies the characteristics and requirements for interactive data services using binary format for scene (BIFS) in the terrestrial digital multimedia broadcasting (T-DMB) receiver.

    • sale 15% off
    • Standard
      38 pages
      English and French language

ISO 26802:2010 specifies the applicable requirements related to the design and the operation of containment and ventilation systems of nuclear power plants and research reactors taking into account the following. For nuclear power plants, ISO 26802:2010 addresses only reactors that have a secondary confinement system based on IAEA recommendations. For research reactors, ISO 26802:2010 applies specifically to reactors for which accidental situations can challenge the integrity or leak-tightness o...view more

    • sale 15% off
    • Standard
      84 pages
      English language
    • sale 15% off
    • Standard
      87 pages
      French language

The scope of IEC 61008-1 and IEC 61009-1 applies with the following additions. IEC 62423:2009 specifies requirements and tests for Type F and Type B RCDs (Residual Current Devices). Requirements and tests given in this standard are in addition to the requirements of Type A residual current devices. This standard can only be used together with IEC 61008-1 and IEC 61009-1. Type F RCCBs (Residual Current Circuit Breaker) and Type F RCBOs (Residual current Circuit Breaker with Overcurrent protection...view more

    • sale 15% off
    • Standard
      74 pages
      English and French language

IEC 60768:2009 provides criteria for the design, selection, testing, calibration and functional location of equipment for the monitoring of radioactive substances within plant-process streams during normal operation conditions and anticipated operational occurrences. Is only applicable to continuous in-line or on-line measurement. This new edition includes the following significant technical changes with respect to the previous edition:
- it clarifies the definitions;
- up-dates the reference ...
view more

    • sale 15% off
    • Standard
      79 pages
      English and French language

IEC 61000-4-28:1999+A1:2001+A2:2009 establishes a reference for evaluating the immunity of electric and electronic equipment when subjected to variations of the power frequency. Only conducted phenomena are considered, including immunity tests for equipment connected to public and industrial networks. This consolidated version consists of the first edition (1999), its amendment 1 (2001) and its amendment 2 (2009). Therefore, no need to order amendments in addition to this publication.

    • sale 15% off
    • Standard
      29 pages
      English and French language

IEC/TR 62096:2009 is intended to support owners of a nuclear power plant in the decision-making process and in the preparation for partial or complete modernization of the I&C. For this, it provides a summary of the motivating factors for I&C modernization, the principal options for the elaboration of different scenarios for I&C modernization, the technical and economic criteria for the selection of a long term I&C strategy, the principal aspects to be taken into account for a detailed technical...view more

    • sale 15% off
    • Technical report
      103 pages
      English and French language

Specifies methods for the determination of mass gain and for the surface inspection of products of zirconium and its alloys when corrosion tested in water at 360 °C or in steam at or above 400 °C. Applicable to wrought products, castings and powder metallurgical products.

    • sale 10% off
    • Standard
      16 pages
      English language
    • e-Library read for
      1 day

See the scope of IEC/IEEE 60980-344:2020. Adoption of IEC/IEEE 60980-344:2020is to be done without modification.

    • sale 10% off
    • Standard
      85 pages
      English language
    • e-Library read for
      1 day
    • sale 10% off
    • Draft
      85 pages
      English language
    • e-Library read for
      1 day

Is applicable to capacitors according to IEC 60110-1 and gives the requirements for the ageing test, destruction test and requirements for disconnecting internal fuses for these capacitors.

    • sale 15% off
    • Technical specification
      31 pages
      English and French language

Is applicable both to indoor capacitor units and indoor capacitor banks intended to be used, particularly, for power factor correction in induction heating, melting, stirring or casting installations, and similar applications with controlled or adjustable a.c. voltage systems in a frequency range up to 50 kHz, and with a rated voltage not exceeding 3,6 kV.

    • sale 15% off
    • Standard
      59 pages
      English and French language

Deals with the standard conditions and methods of measurement on high definition television (HDTV) displays. Deals with the determination of performance and permits comparision of equipment by listing characteristics useful for specifications and laying down uniform methods of measurement.

    • sale 15% off
    • Standard
      129 pages
      English and French language

Specifies methods for the determination of mass gain and for the surface inspection of products of zirconium and its alloys when corrosion tested in water at 360 °C or in steam at or above 400 °C. Applicable to wrought products, castings and powder metallurgical products.

    • sale 15% off
    • Standard
      11 pages
      English language
    • sale 15% off
    • Standard
      12 pages
      French language
    • sale 15% off
    • Standard
      12 pages
      French language

Provides the basis for calculating the decay heat power of non-recycled nuclear fuel considering: the contribution of the fission products from nuclear fission; the contribution of the actinides; the contribution of isotopes resulting from neutron capture in fission products.

    • sale 15% off
    • Standard
      12 pages
      English language
    • sale 15% off
    • Standard
      13 pages
      French language
    • sale 15% off
    • Standard
      13 pages
      French language

Is applicable to all operations with plutonium, uranium 233, uranium enriched in the 235 isotope, and other fissionable materials. Does not require separate additional instrumentation when the operating instrumentation of the facilities meets its requirements. Is principally concerned with gamma-radiation rate-sensing systems. Annex A refers to the specification of a minimum accident of concern, annex B provides examples of application, and annex C provides guidance for development of emergency ...view more

    • sale 15% off
    • Standard
      9 pages
      English language
    • sale 15% off
    • Standard
      9 pages
      French language
    • sale 15% off
    • Standard
      9 pages
      French language

This document defines the essential technical requirements that are addressed in the process of design and construction of Generation IV (GEN IV) nuclear reactors. It does not address operation, maintenance and in-service inspection of reactors.
Six reactor concepts are considered for GEN IV: the sodium fast reactor, the lead fast reactor, the gas fast reactor, the very high temperature reactor, the supercritical water reactor and the molten salt reactor.
Annex A details the main characteristi...
view more

    • sale 10% off
    • Draft
      35 pages
      English language
    • e-Library read for
      1 day

This document defines the essential technical requirements that are addressed in the process of design and construction of Generation IV (GEN IV) nuclear reactors. It does not address operation, maintenance and in-service inspection of reactors.
Six reactor concepts are considered for GEN IV: the sodium fast reactor, the lead fast reactor, the gas fast reactor, the very high temperature reactor, the supercritical water reactor and the molten salt reactor.
Annex A details the main characteristi...
view more

    • sale 10% off
    • Draft
      35 pages
      English language
    • e-Library read for
      1 day

Applies to equipment for the monitoring of radioactive substances within plant process streams of stationary nuclear power plants with light-water reactors during specified normal operation (routine operation) and during anticipated operational occurrences (incidents). Provides criteria for the design, selection, functional location, testing and calibration of stationary radiation equipment to be used for continuous monitoring of plant process streams.

    • sale 10% off
    • Standardization document
      11 pages
      English language
    • e-Library read for
      1 day

Specifies requirements for the unique identification. Was developed primarily for commercial light-water reactor fuel, but may be used for any reactor fuel contained in discrete fuel assemblies that can be identified with an identification code. Defines the characters and proposed sequence to be used in assigning identification to the fuel assemblies. The identification is intended to be borne by the fuel assembly throughout its lifetime. Aims at providing an organizing principle for fuel assemb...view more

    • sale 15% off
    • Standard
      4 pages
      English language
    • sale 15% off
    • Standard
      4 pages
      French language
    • sale 15% off
    • Standard
      4 pages
      French language