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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.
Kostadin N. Ivanov, Tara M. Beam, Anthony J. Baratta, Ardesar Irani, Nicholas G. Trikouros
Nuclear Technology | Volume 133 | Number 2 | February 2001 | Pages 169-186
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3167
Articles are hosted by Taylor and Francis Online.
A comparison of a point-kinetics calculation and a full three-dimensional thermal-hydraulic/kinetics calculation using TRAC-PF1/NEM is presented. The coupled TRAC-PF1/NEM methodology uses version 5.4 of the TRAC-PF1/MOD2 code, developed by the Los Alamos National Laboratory, and a special kinetics module, developed at The Pennsylvania State University and based on the nodal expansion method. Cross sections are obtained from two-dimensional tables generated using CASMO-3.The results of the analysis show that the point-kinetics calculation is conservative and predicts a return to power. The three-dimensional analysis shows no return to power despite an extended overfeeding of the affected generator with feedwater. The difference is believed to be caused by the inability of the standard point-kinetics method to properly account for the moderator density feedback, local effects, and flux redistribution, which occur during the transient.
