Working Group

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.

Scope: This standard establishes a standardized protocol for analyzing oxygen concentration in molten salts using inert gas fusion analysis. The comprehensive methodology includes the development of precise analytical procedures, optimized sample preparation techniques, and detailed analysis protocols to ensure accuracy and repeatability. The standardization effort covers a broad range of analyzers, ensuring compatibility and reliability across different instrumentation. This work aims to provide a universally applicable guideline for determining oxygen content in molten salts, facilitating consistency and comparability between users.

Scope: This standard provides criteria for the testing of nuclear reactors to be utilized for in-space related applications such as the production of electrical power for use on space platforms, on the surface of the moon or other solar system bodies and for the propulsion of space platforms and vehicles. This standard provides criteria to be used by the developers, analyzers, and evaluators of space reactors when considering the ground and in-space testing of space reactors and their associated equipment, as well as the facilities in which such testing is conducted. This standard is intended to be design, mission, sponsor, location, and facility agnostic.

Scope: This standard provides a process for establishing top-level safety criteria (TLSC); safety functions; top-level design criteria (TLDC); potential licensing-basis events (LBEs); potential design-basis accidents (DBAs); safety classification of systems, structures, and components (SSCs); safety analyses; defense-in-depth (DID); and adequate assurance of special treatment requirements for safety-related SSCs throughout the operating life of the plant. This standard does not provide detailed guidance for design.

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.

Scope: This standard establishes guidelines and requirements to ensure that the fundamental performance of liquid-metal fire detection, alarm, suppression, control, and structural protection systems are adequate to protect the public health and safety, facility personnel, and minimize or limit the economic loss in the event of a sodium/NaK leak.