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NRC approves TerraPower construction permit
Today, the Nuclear Regulatory Commission announced that it has approved TerraPower’s construction permit application for Kemmerer Unit 1, the company’s first deployment of Natrium, its flagship sodium fast reactor.
This approval is a significant milestone on three fronts. For TerraPower, it represents another step forward in demonstrating its technology. For the Department of Energy, it reflects progress (despite delays) for the Advanced Reactor Demonstration Program (ARDP). For the NRC, it is the first approval granted to a commercial reactor in nearly a decade—and the first approval of a commercial non–light water reactor in more than 40 years.
F. Nagase, R. O. Gauntt, M. Naito
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 499-510
Technical Paper | doi.org/10.13182/NT16-10
Articles are hosted by Taylor and Francis Online.
The Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF) project, run by the Organisation for Economic Co-operation and Development/Nuclear Energy Agency, was established in November 2012. The primary objectives of this benchmark study are to estimate accident progression and status inside the nuclear reactors, including the distribution of fuel debris, and consequently, to contribute to the decommissioning activity at the Fukushima Daiichi nuclear power plant. Altogether, 17 organizations from eight countries calculated the thermohydraulic behavior inside the three reactors for the time span of about 6 days from the occurrence of the earthquake with their severe accident integral codes. Since many boundary conditions are unknown for the accident, those necessary for the calculation were discussed and determined by the participants.
The results submitted were compared on coolant level change, hydrogen generation, initiation and progression of melt in fuel bundle and control blade, failure of reactor pressure vessel, distribution and composition of molten and solidified materials, and progression of the molten core–concrete interaction. Finally, the current estimates of the accident progression and status inside the reactors were summarized together with the still remaining uncertainties and data needs as the output from the project.