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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.
A. R. Raffray, F. Escourbiac, F. J. Fuentes, L. Giancarli, B. Macklin, A. Martin, M. Merola, R. Mitteau, J. Palmer
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 465-476
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-945
Articles are hosted by Taylor and Francis Online.
The overall programmatic objective of ITER is to demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes. The physics part of this objective (including burning plasma, Q of at least 10 and stationary conditions) seems to be well appreciated by the scientific community internationally. However, there seems to be less of an emphasis on the fusion technology part of the objective, which includes demonstrating the availability and integration of technologies essential for a fusion reactor and testing components including tritium breeding blanket modules for a future reactor. In fact important technology information will be obtained from the design, fabrication and operation of the vacuum vessel and out-of-vessel systems such as magnets, tritium system, cryogenic systems, cooling water systems, and associated safety aspects. In addition, DEMO-relevant information will be obtained from the operation of breeding blanket test modules in ITER. Moreover valuable information applicable to DEMO and beyond will also be obtained in a number of areas linked to in-vessel components. This paper summarizes the DEMO-relevant fusion technology information that will be obtained from ITER with a major focus on the areas linked to in-vessel components.