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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.
D. H. Meikrantz, J. D. Baker, G. L. Bourne, R. J. Pawelko, R. A. Anderl, D. G. Tuggle, H. R. Maltrud
Fusion Science and Technology | Volume 27 | Number 2 | March 1995 | Pages 14-18
doi.org/10.13182/FST95-A11963799
Articles are hosted by Taylor and Francis Online.
A zirconium alloy getter-based tritium monitoring and collection system has been designed, built, and subsequently operated for three years at the Idaho National Engineering Laboratory. The system is automated to provide separation of tritium from 41Ar, collection of tritium on an hourly basis, unloading of getters for on-line tritium measurement via an ion chamber, and recollection of tritium on removable getters for daily assay in the laboratory. Three different SAES Getters alloys are employed to purify the gas stream (St 909), and separate the tritium from Ar and collect the tritium for measurement (St 727 and St 707). This system has demonstrated on-line tritium measurements as low as 20 μCi per sample with typical decontamination factors from 41Ar of 107. In addition, laboratory studies aimed at the recovery of tritium from graphitic targets have demonstrated further process applications for these getters. Prototypical gas cooled reactor targets, containing encapsulated 6Li, were irradiated at the Advanced Test Reactor at this laboratory. Samples were then heated to high temperatures to allow diffusive release of the tritium into a flowing helium stream. St 909 purifier and St 727 collector getters have been employed to demonstrate an efficient tritium recovery process.