American Nuclear Society
Home

Home / Standards / Get Involved / Volunteer Opportunities / Research and Advanced Reactors (RAR) Consensus Committee / Advanced Initiatives

Working Group

If you are interested in participating in the following standards, complete and submit the Standards Volunteer Form.

ANS-20.1, Nuclear Safety Criteria and Design Process for Fluoride Salt-Cooled High-Temperature Reactor Nuclear Power Plants

Scope: This standard establishes the nuclear safety criteria, and design requirements for the Fluoride salt-cooled High-temperature Reactor nuclear power plants. Performance-based, risk-informed criteria are used wherever possible. It describes the design process to be followed to establish those criteria and perform structures, systems, and component classifications.

ANS-53.1, Nuclear Safety Design Process for Modular Helium-Cooled Reactor Plants

Scope: This standard establishes the nuclear safety criteria, functional performance and design requirements of structures, systems, and components (SSC) for modular helium reactor (MHR) plants applicable to performance-based, risk-informed regulation.

ANS-54.1, Nuclear Safety Criteria and Design Process for Liquid-Sodium-Cooled Nuclear Power Plants

Scope: This standard establishes the nuclear safety criteria, functional performance and design requirements for liquid-sodium-cooled nuclear power plants. The document uses performance-based, risk-informed PRA criteria wherever possible. It also describes the design process to be followed to establish those criteria and perform structures, systems, and component classifications.

Last updated July 22, 2014, 3:02pm CDT.

 
Questions or comments about the site? Contact the ANS Webmaster.
advertisement