ISO TC 85/SC 6

Reactor technology    

Paris - Septembre 2025

 

Its scope

Standardization in the field of nuclear power plants and research reactors.

The scope includes calculation, analysis and measurements in support of physics of power reactor core design and operation, siting, design, construction, operation and decommissioning.

Siting includes all types of nuclear installations and all topics such as flooding, seismic hazards, etc.

Research reactors include a large variety of facilities: production of neutron beams, irradiation of specimens, production of isotopes (especially production for nuclear medicine) and test reactors or prototypes of new technologies.

Excluded: decommissioning is limited to technical topics that are specific to reactors.

Its structure

WG 1 - Power reactor analyses and measurements

WG 2 - Research, test and isotope-production reactors

WG 3 - Power reactor, siting, design, construction, operation, and decommissioning

For more information

Its objectives

• to present the current status of ISO standards within the scope of SC 6,
• to identify gaps in the current scope,
• to identify related standardization activities in other organizations in order to minimize duplication and non-conformity,
• to identify topics for new ISO standards, taking into account the needs of the industry and conformity with standards of other international organizations, such as IAEA, IEC, etc.
• to gain and maintain momentum, visibility and recognition to attract experts from the whole community (industry, regulatory bodies, technical support organizations …) and from all Member States to produce industrial standards of high quality and added value

The Potential future works

• nuclear data for radioisotopes production for medical and industrial applications
• neutron fission yields
• delayed Neutrons
• nuclear Data for reactor design
• cold neutron sources
• fusion reactors (ITED)
• general requirements for research reactors (design, operation, decommissioning and waste management)
• construction and design
• external hazards
• inspection methods or specific topics
• SMR
• generation IV reactors