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The transformation of the NRC: 50 years of commissioners
The dust is beginning to settle following the whirlwind of changes at the Nuclear Regulatory Commission over the past year, and 2025 ultimately may be viewed as a transformative year, as well as the year the NRC celebrated its golden anniversary. The 12 months of that milestone year brought more change to the agency in its composition, its mandate, and its relationship to the executive branch than any comparable period in the preceding four decades.
Now at 51 years and counting, the NRC is working with a full commission and issuing new rulemakings to both regulate and support the next round of nuclear deployments. With the turbulence of 2025 still fresh in our minds, Nuclear News decided it was a good time to revisit the professional backgrounds of all 42 NRC commissioners who have served over the agency’s 50-year history to see how the composition of the commission has evolved over time.
Wang Kai, Xiaowei Jiao, Chuangxiong Cai, Zhaozhong He, Kun Chen (CAS)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1199-1204
Direct auxiliary cooling system (DRACS) is one candidate for FHR (Fluoride-salt-cooled High temperature reactor) decay heat removal system. DRACS relies on buoyancy as the driving force to form natural circulation to remove the decay heat. As a passive engineered safety feature, some key parameters and models must be validated. In order to study the characteristics of the natural circulation of the molten salts, a high-temperature molten salt natural circulation experiment loop has been designed and constructed by the TMSR (Thorium Molten Salt Reactor) center of the Chinese Academy of Sciences (CAS) with nitrate selected to be coolant. A series of experiments have been scheduled to be conducted on the loop, this loop could be used as a validation facility for DRACS. In this paper, steady-state natural circulation experiment results are shown. The results show that NNCL (nitrate natural circulation loop) was running steady and reliable, and the heat can be removed continuously. The RELAP5-MS code is employed to simulate NNCL behavior, and the simulation results coincide with experiment results. The modified RELAP5-MS can be used for the molten salt natural circulation system analysis. Based on these experiments and simulation results, the DRACS system can be used in the molten salt reactor as the decay heat removal system.