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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.
Canhui Sun, Zhaocan Meng, Yaodong Chen (State Power Investment Corp. Research Inst)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1153-1160
Rapid industrialization and urbanization in the last 30 years in China have caused severe air pollution. In order to meet the new challenges on the energy and environment, a new conceptual design of nuclear heating reactor (HAPPY200) is developed. HAPPY200 is a two-loop low pressure water reactor with low thermal parameters and passive safety systems. It can be used for heating, cooling, desalination and other process heat applications. Based on large volume pool completely passive technologies, HAPPY200 safety system can provide an inherent technical guarantee for the safety of the reactor.
The thermal-hydraulic behavior analysis is necessary for the safety and economy of the design. Subchannel analysis is the basic thermal-hydraulic analysis method used to predict the coolant enthalpy, quality, density, mass velocity rate, liquid temperature, vapor void fraction, pressure distribution, and the resulting DNBR distributions.
In this study, the analysis of thermal-hydraulic behavior for low pressure reactor is worked. Some problems are discussed for low pressure reactor, and the subchannel object model is established by subchannel code. Some low pressure CHF correlations developed for other fuel assemblies are analyzed. The thermal diffusion coefficient for reduced-height rod bundle is obtained compared with full-height rod bundle using CFD code. The value of reduced-height rod bundle can be used in the preliminary analysis of HAPPY200. According to the subchannel results, all the values satisfy conceptual design criteria.
