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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.
Bei Ye, Jeff Rest, Yeon Soo Kim, Gerard Hofman, Benoit Dionne
Nuclear Technology | Volume 191 | Number 1 | July 2015 | Pages 27-40
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-56
Articles are hosted by Taylor and Francis Online.
DART (Dispersion Analysis Research Tool) is a computational code developed for integrated simulation of the irradiation behavior of aluminum dispersion fuels used in research reactors. The DART computational code uses a mechanistic fission gas behavior model and a set of up-to-date empirical correlations to simulate the fuel morphology change as a function of burnup. Integrating a thermal calculation subroutine enables fuel material properties to be updated at each time step. This paper describes the primary physical models that form the basis of the DART computational code. A baseline validation was performed through the modeling of several U-Mo/Al mini-plate tests (RERTR-6, 7, and 9) in the Advanced Test Reactor (ATR). A demonstration problem is also presented through the calculation of fuel plate swelling and constituent volume fractions in full-sized plates from the AFIP-1 test in ATR.