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NRC unveils Part 53 final rule
The Nuclear Regulatory Commission has finalized its new regulatory framework for advanced reactors that officials believe will accelerate, simplify, and reduce burdens in the new reactor licensing process.
The final rule arrives more than a year ahead of an end-of-2027 deadline set in the Nuclear Energy Innovation and Modernization Act (NEIMA), the 2019 law that formally directed the NRC to develop a new, technology-inclusive regulatory approach. The resulting rule—10 CFR Part 53, “Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors”—is commonly referred to as Part 53.
Giacomo G. M. Cojazzi, Guido Renda, Jor Shan Choi, Jim Hassberger
Nuclear Technology | Volume 179 | Number 1 | July 2012 | Pages 76-90
Technical Paper | Special Issue on Safeguards / Fuel Cycle and Management | doi.org/10.13182/NT179-76
Articles are hosted by Taylor and Francis Online.
The Generation IV International Forum (GIF) Proliferation Resistance and Physical Protection (PR&PP) Working Group has developed a methodology for the PR&PP evaluation of advanced nuclear energy systems (NESs). A notional sodium-cooled fast neutron nuclear reactor system, named the Example Sodium Fast Reactor (ESFR), was used as a case study for the development and demonstration of the GIF PR&PP evaluation methodology. This paper presents some of the results of the application of the GIF PR&PP evaluation methodology to a misuse scenario involving the ESFR. The ESFR baseline design and two design variations are addressed. Rather than presenting a complete evaluation of all the possible misuse scenarios, the paper concentrates on methodological aspects and illustrates how a qualitative analysis following the GIF PR&PP evaluation methodology can generate traceable results of the considered design variations and provide useful feedback for both system and safeguards designers as well.
