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Reactor technology

Established on 23rd Feb 1947, The International Organization for Standardization (ISO), is an independent, non-governmental international standards development organization having representatives from various national standards organizations of member countries. ISO is a network of 167 member countries, with a Central Secretariat in Geneva, Switzerland that coordinates the system.

ISO has published 24, 676 International Standards covering all technical & non-technical fields other than electrical & electronic engineering which are the responsibility of IEC.

It could be about making a product, managing a process, delivering a service or supplying materials – ISO standards cover a huge range of activities.

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Design of nuclear power plants against seismic events — Part 5: Seismic instrumentation

ISO 4917-5:2024

Design of nuclear power plants against seismic events — Part 5: Seismic instrumentation

Design of nuclear power plants against seismic events — Part 4: Components

ISO 4917-4 : 2024

Design of nuclear power plants against seismic events — Part 4: Components

Design of nuclear power plants against seismic events — Part 6: Post-seismic measures

ISO 4917-6 : 2024

Design of nuclear power plants against seismic events — Part 6: Post-seismic measures

Design of nuclear power plants against seismic events — Part 3: Civil structures

ISO 4917-3 : 2024

Design of nuclear power plants against seismic events — Part 3: Civil structures

Design of nuclear power plants against seismic events — Part 1: Principles

ISO 4917-1 : 2024

Design of nuclear power plants against seismic events — Part 1: Principles

Nuclear power plants — Maintainability — Terminology

Nuclear power plants — Maintainability — Terminology

Nuclear energy — Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals

Nuclear energy — Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals

Steady-state neutronics methods for power-reactor analysis

Steady-state neutronics methods for power-reactor analysis

Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors

Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors

Method for the justification of fire partitioning in water cooled nuclear power plants (NPP)

Method for the justification of fire partitioning in water cooled nuclear power plants (NPP)

Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 1: Mechanized ultrasonic testing

ISO 20890-1:2020

Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 1: Mechanized ultrasonic testing

Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 5: Eddy current testing of steam generator heating tubes

ISO 20890-5:2020

Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 5: Eddy current testing of steam generator heating tubes

Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 2: Magnetic particle and penetrant testing

ISO 20890-2:2020

Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 2: Magnetic particle and penetrant testing

Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 4: Visual testing

ISO 20890-4:2020

Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 4: Visual testing

Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 3: Hydrostatic testing

ISO 20890-3:2020

Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 3: Hydrostatic testing

Group-averaged neutron and gamma-ray cross sections for radiation protection and shielding calculations for nuclear reactors

Group-averaged neutron and gamma-ray cross sections for radiation protection and shielding calculations for nuclear reactors

Identification of fuel assemblies for nuclear power reactors

Identification of fuel assemblies for nuclear power reactors

Reactor technology — Power reactor analyses and measurements — Determination of heavy water isotopic purity by Fourier transform infrared spectroscopy

Reactor technology — Power reactor analyses and measurements — Determination of heavy water isotopic purity by Fourier transform infrared spectroscopy

Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants

Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants

Ice plug isolation of piping in nuclear power plant

Ice plug isolation of piping in nuclear power plant

Nuclear energy — Light water reactors — Decay heat power in non-recycled nuclear fuels

Nuclear energy — Light water reactors — Decay heat power in non-recycled nuclear fuels

Reload startup physics tests for pressurized water reactors

Reload startup physics tests for pressurized water reactors

Reactor technology — Nuclear fusion reactors — Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors

Reactor technology — Nuclear fusion reactors — Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors

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