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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.
Richard Babut, Olivier Bouland, Eric Fort
Nuclear Science and Engineering | Volume 151 | Number 2 | October 2005 | Pages 135-156
Technical Paper | doi.org/10.13182/NSE05-A2536
Articles are hosted by Taylor and Francis Online.
Evaluated data are adjusted on experimental measurements using nuclear reaction models. Among these data, those concerning alpha-particle interactions on light nuclei are not well known, although crucial for neutron emission problems via (,n) processes in nuclear fuels (oxide, carbide, nitride). Examples of applications are reprocessing, packaging and storage of radioactive waste, and intrinsic neutron source term evaluation in critical and subcritical reactors (accelerator-driven systems). The goal is the modeling of (,n) reactions on oxygen isotopes to extract the resonance parameters. The SAMMY code, which relies on the Reich-Moore approximation of the R-matrix theory, is used. In the most recent version, the SAMMY code allows the study of the in- and outgoing charged-particle channels. An important validation of this new feature has been made. In addition, a manifest lack of experimental data for this type of reaction has been underlined. Finally, the impact of the new pointwise description of the (,n) reaction cross section on the energy distribution calculation of the intrinsic neutron source of an irradiated mixed-oxide fuel pin is shown and compared to the standard calculation, which uses average cross sections.