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ANSI/ANS-20.2-2023

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


This standard (1) provides design criteria for liquid-fuel molten salt reactors that match the safety intent of the Code of Federal Regulations Title 10, Part 50, Appendix A, general design criteria following an equivalent process to that performed by NRC Regulatory Guide 1.232 for modular high-temperature gas-cooled reactors and sodium-cooled fast reactors; (2) provides definitions of molten salt reactors terminology important for safety evaluation; (3) describes distinctive safety considerations for MSRs; and (4) provides a molten salt reactor-focused description of a risk-informed design process following the methodology described in NEI 18-04 and ANSI/ANS-53.1-2011 (R2021).


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American National Standards Institute [ansi]

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