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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.
Thomas B. Rezentes, Mark A. Prelas, Eric Lukosi, Matthew L. Watermann, Jack Crawford, and Richard H. Olsher
Nuclear Technology | Volume 187 | Number 1 | July 2014 | Pages 96-102
Technical Note | Radiation Transport and Protection | doi.org/10.13182/NT11-105
Articles are hosted by Taylor and Francis Online.
A computer-based investigative technique, using the Los Alamos Monte Carlo code MCNP5 version 1.51 (Radiation Safety Information Computational Center), was completed to assess the shallow dose equivalent (SDE) reported on the Landauer, Inc.,TM Luxel+ optically stimulated light (OSL) dosimeter. Experimental test irradiations were conducted on 18 OSL dosimeters through various controlled exposures to the source (10 mCi 90Sr). The reported SDE for each test irradiation was compared to the results for SDE calculated using MCNP5. All test irradiation experiments were conducted with the 90Sr source placed in direct contact with the dosimeter with slight placement changes across the dosimeter face. It was found that these slight adjustments caused vast differences in reported doses by Landauer. The SDE determined in a tissue matrix using MCNP5 was studied for two of the dosimeter badge geometries, and it was found that some qualitative agreement exists between the reported and simulated doses in contradiction with the experimental results. Further simulated analysis was not conducted because precise source-dosimeter geometries and the algorithm used by Landauer to analyze its Luxel+ OSL dosimeters were not known. These results indicate that a future study should be conducted with more rigorous simulated benchmarking to verify these results.