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Developing a new regulatory framework for advanced reactors: Update on Part 53
White
The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) on March 29 held another presentation in its monthly Community of Practice (CoP) series. The presenter, Patrick White with the Nuclear Innovation Alliance (NIA), talked about the current status of efforts to develop a new regulatory framework for advanced reactors—known as 10 CFR Part 53 or simply Part 53. White serves as the research director of the NIA, where he leads their research as well as analysis-based stakeholder and policymaker engagement and education. White’s March 29 presentation is publicly available on YouTube and at ANS’s publication platform Nuclear Science and Technology Open Research (NSTOR).
RP3C chair N. Prasad Kadambi opened the CoP with brief introductory remarks about the RP3C before he welcomed White as the session’s presenter.
White covered three main topics: the history of the existing regulatory frameworks for new reactors, progress to date on the development of the Part 53 rule for advanced reactors, and the current status and next steps for the Part 53 rulemaking process.
Toyoshi Fuketa, Hideo Sasajima, Tomoyuki Sugiyama
Nuclear Technology | Volume 133 | Number 1 | January 2001 | Pages 50-62
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3158
Articles are hosted by Taylor and Francis Online.
Experimental programs on fuel behavior during simulated reactivity-initiated-accident (RIA) conditions at the Nuclear Safety Research Reactor (NSRR) in Japan and the CABRI test reactor in France appear to indicate that cladding failures may occur at enthalpy values lower than would be expected. Results from two experiments designated as HBO-1 in NSRR and REP Na-1 in CABRI indicate that the occurrence of fuel failure is strongly influenced by corrosion of cladding in the tested fuels. However, data had been limited to fuel rods with conventional (1.5% Sn) Zircaloy-4 cladding. Results are described from newly conducted NSRR experiments, TK test series, for 38 to 50 MWd/kg U pressurized water reactor fuels with low-tin (1.3% Sn) Zircaloy-4 cladding, and anticipated processes of fuel behavior during the transient are discussed.
