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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Ho Nieh nominated to the NRC
Nieh
President Trump recently nominated Ho Nieh for the role of commissioner in the Nuclear Regulatory Commission through the remainder of a term that will expire June 30, 2029.
Nieh has been the vice president of regulatory affairs at Southern Nuclear since 2021, though he is currently working as a loaned executive at the Institute of Nuclear Power Operations, where he has been for more than a year.
Nieh’s experience: Nieh started his career at the Knolls Atomic Power Laboratory, where he worked primarily as a nuclear plant engineer and contributed as a civilian instructor in the U.S. Navy’s Nuclear Power Program.
From there, he joined the NRC in 1997 as a project engineer. In more than 19 years of service at the organization, he served in a variety of key leadership roles, including division director of Reactor Projects, division director of Inspection and Regional Support, and director of the Office of Nuclear Reactor Regulation.
Edward A. Boucheron, John E. Kelly
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 1050-1057
Late Paper | TMI-2: Decontamination and Waste Management / Nuclear Safety | doi.org/10.13182/NT89-A27696
Articles are hosted by Taylor and Francis Online.
The MELCOR computer code has been used to analyze the first 174 min of the Three Mile Island Unit 2 (TMI-2) accident. MELCOR is being developed at Sandia National Laboratories for the U.S Nuclear Regulatory Commission for the purpose of analyzing severe accidents in nuclear power plants. Comparison of the code predictions to the available data shows that MELCOR is capable of modeling the key events of the TMI-2 accident, and reasonable agreement with the available data is obtained. In particular, the core degradation and hydrogen generation models agree with best-estimate information available for this phase of the accident. While the code uses simplified modeling, all important characteristics of the reactor system and the accident phenomena could be modeled. This exercise demonstrates that MELCOR is applicable to severe accident analysis.
