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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.
Povilas Poskas, Raimondas Kilda, Valdas Ragaisis, Terry M. Sullivan
Nuclear Technology | Volume 161 | Number 2 | February 2008 | Pages 140-155
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT08-A3919
Articles are hosted by Taylor and Francis Online.
Safety assessment of a near-surface repository of radioactive waste usually assumes a homogeneous distribution of activity within the vaults of the repository. However, in some cases there is radioactive waste, e.g., disused sealed sources, which should result in so-called "hot spots" when disposed of with other radioactive waste. An uneven distribution of waste activity is obtained in that case.The impact of heterogeneities in source distribution on radionuclide releases from a near-surface repository to the groundwater is analyzed in the paper. The conditions that stand for the application of homogeneous distribution of radioactive waste are revealed.The assessment has been performed using the methodology of the Improving Long Term Safety Assessment Methodologies for Near Surface Radioactive Waste Disposal Facilities (ISAM) study recommended by the International Atomic Energy Agency for the safety analysis of the near-surface repository. A description of the ISAM methodology and its application for the analysis of heterogeneity including a brief description of the disposal system of radioactive waste, the scenarios for the radionuclide migration, and the developed conceptual models are presented in the paper.The calculations have been carried out using the DUST and GWSCREEN computer codes, designed to simulate radionuclide transport. The modeling results for the case of homogeneous distribution of radioactive waste in the repository are considered. The impact of heterogeneities has been analyzed by comparing the modeling results of radionuclide transport for the heterogeneous case of waste distribution to the homogeneous case.