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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.
R. Crasta, S. Ganesh, H. Naik, A. Goswami, S. V. Suryanarayana, S. C. Sharma, P. V. Bhagwat, B. S. Shivashankar, V. K. Mulik, P. M. Prajapati
Nuclear Science and Engineering | Volume 178 | Number 1 | September 2014 | Pages 66-75
Technical Paper | doi.org/10.13182/NSE11-90
Articles are hosted by Taylor and Francis Online.
The (n,γ) and (n,2n) capture cross sections of 238U have been measured at neutron energies of 8.04 ± 0.30 and 11.90 ± 0.35 MeV from the 7Li(p,n) reaction using an activation and off-line gamma-ray spectrometric technique. The experimentally determined 238U(n,γ) and 238U(n,2n) reaction cross sections were compared with the evaluated data of ENDF/B-VII.0, JENDL-4.0, JEFF-3.1/A, and CENDL-3.1. The experimental values were found to be in agreement with the evaluated value based on ENDF/B-VII.0, JENDL-4.0, and JEFF-3.1/A but not with CENDL-3.1. The present measurement has been compared with literature data in a wide range of neutron energies. The 238U(n,γ)239U and 238U(n,2n)237U reaction cross sections were also calculated theoretically using the TALYS 1.4 computer code and compared with the experimental data.