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-30.1, Risk-Informed and Performance-Based Nuclear Power Plant Design Process

Scope: The nuclear industry is actively investigating non-light-water (NLW) reactor technologies to supplement designs based on traditional light water (LWR) technologies. However, available ANS design standards for these NLW technologies are generally not available or are outdated. The application of traditional LWR design standards to smaller modular and passive LWR designs has also not been clearly articulated. Further, existing design standards are primarily deterministic-based due to the historical lack of risk-informed, performance-based (RIPB) methods. RIPB methods are now available and can provide a comprehensive characterization of design issues commensurate with their importance to health and safety. It is proposed that a new standard ANS-30.1 be prepared that is technology-neutral, process-based, and provides an acceptable methodology for incorporating RIPB information into the nuclear safety criteria and functional design requirements of new and non-traditional nuclear plant designs. The objective of ANS 30.1 is to provide an upper tier methodology from which adjunct, technology-specific design criteria standards may be generated. The ANS-30.1 standard will address applicable regulatory requirements, both past (as applicable) and current, maintain sufficient safety margins, and will treat nuclear plant design issues commensurate with their impact on health and safety.

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