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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.
E. T. Cheng
Fusion Science and Technology | Volume 44 | Number 2 | September 2003 | Pages 549-553
Technical Paper | Fusion Energy - Nonelectric Applications | doi.org/10.13182/FST03-A395
Articles are hosted by Taylor and Francis Online.
A fusion based actinide destruction system is advantageous because of higher actinide destruction efficiency and higher energy efficiency when compared to other destruction technologies. The unique neutron multiplication capability due to the n,2n reactions in blanket materials with 14 MeV D-T neutrons enhances further the performance efficiency.Investigation of a high performance fusion based actinide destruction system was conducted. A self-cooled, actinide-carrying molten salt blanket can be designed to operate at a high sub-criticality factor of 0.95-0.96, with less than 0.4 wt% actinide concentration dissolved in the molten salt. The corresponding blanket energy multiplication is 160. Lithium-6, which is required for tritium breeding, can be used as a variable to shape the neutron spectrum and control the criticality factor, and thus to maintain a constant fission thermal power output from the actinide destruction plant.Sub-criticality can be maintained in all cases of the actinide destruction plant, during normal operation and abnormal conditions.A fusion device projected from a tokamak experiment can produce 30 MW fusion power, with a plasma amplification factor of 2. It is considered adequate to drive the sub-critical molten salt blanket. The total thermal fission power is about 4000 MW, which is able to destroy 1.6 metric tons of actinides annually when operating at full power.