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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.
M. E. Rensink, T. D. Rognlien
Fusion Science and Technology | Volume 67 | Number 1 | January 2015 | Pages 125-141
Technical Paper | doi.org/10.13182/FST14-800
Articles are hosted by Taylor and Francis Online.
Simulations of the heat flux on plasma-facing components from core exhaust plasma are reported for two possible ACT1 divertor configurations. One configuration uses divertor plates strongly inclined with respect to the poloidal magnetic flux surfaces similar to that planned for ITER and results in a partially detached divertor plasma. The second configuration has divertor plates orthogonal to the flux surfaces, which leads to a fully detached divertor plasma if the width of the divertor region is sufficient. Both configurations use scrape-off layer radiation from seeded impurities to yield an acceptable peak heat flux of ∼10 MW/m2 or smaller on the divertor plates and chamber walls. The simulations are performed with the UEDGE two-dimensional transport code to model both plasma and neutral components with some supplementary neutral modeling performed with the DEGAS 2 Monte Carlo code.