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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.
B. H. Mills, B. Zhao, S. I. Abdel-Khalik, M. Yoda
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 541-545
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST15-116
Articles are hosted by Taylor and Francis Online.
A new helium (He) loop was used to study the helium-cooled modular divertor with multiple jets (HEMJ) at incident heat fluxes q″ ≤ 6.6 MW/m2 as part of the joint US-Japan effort on plasma-facing components evaluation by tritium plasma, heat, and neutron irradiation experiments (PHENIX). These studies were performed at prototypical pressures of 10 MPa and inlet temperatures ranging from 30 °C to 300 °C. The effect of varying the distance between the inner jets cartridge and the outer shell from 0.44 to 0.9 mm was also investigated.
The Nusselt number Nu results for two different tungsten-alloy test sections were in good agreement for q″ = 1.5−6.6 MW/m2. The experiments also suggest that the loss coefficient KL is essentially constant. These Nu and KL results were used to estimate the maximum heat flux q′′max that can be accommodated by the divertor under prototypical conditions and the coolant pumping power as a fraction of the incident thermal power β. The agreement over the broad range of experimental parameters studied suggests that these results at near-prototypical conditions can be extrapolated with reasonable confidence to the operating conditions expected for the HEMJ design.