American Nuclear Society
Home

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

Working Group

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

ANS-20.2, Nuclear Safety Design Criteria and Functional Performance Requirements for Liquid-Fuel Molten-Salt Reactor Nuclear Power Plants

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

ANS-30.1, Integrating Risk and Performance Objectives into New Reactor Nuclear Safety Designs

Scope: This standard is technology-neutral and applicable to new reactor designs. It specifies objectives for augmenting deterministic nuclear safety design practices using risk-informed, performance-based (RIPB) methods. The application of RIPB methods to high level safety criteria selection, nuclear safety functions and margin, licensing-basis-event selection, equipment classification, and defense-in-depth adequacy is described to ensure RIPB-augmentation of nuclear safety design practices is consistently applied for all new reactor technologies. The application of this standard to existing reactors is beyond the scope of this standard.

ANS-30.2, Categorization and Classification of Structures, Systems, and Components for New Nuclear Power Plants

Scope: This standard provides a single technology neutral categorization and classification process for Structures, Systems, and Components (SSCs) for new nuclear power plants that is, where possible, risk informed and performance based. This process will then be used to determine special treatment of SSCs to meet the safety basis. This standard applies only to those new design facilities (i.e. greater than Generation III) that must obtain an operating license from the proper regulatory authority. It provides a complete (e.g., necessary and sufficient) repeatable logical process based upon risk-informed, performance based objectives. Other voluntary consensus standards may often be required in order to complete the entire process for all SSCs. Those standards are incorporated by reference.

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 Sodium Fast Reactor Nuclear Power Plants

Scope: This standard applies to all sodium fast reactor nuclear power plants, irrespective of level of power production and energy end use. It also applies to configurations in which there are one or more reactor units (modules) on a site. It is intended to apply to all fuel types. The heat transport system is not restricted to a particular configuration and thus the standard applies to loop, pool, hybrid, or other arrangements. The standard also pertains to on-site storage of spent fuel prior to its removal for recycling or long-term storage.

Last modified July 21, 2016, 1:57pm CDT