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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.
James M. Broughton, Pui Kuan, David A. Petti, and, E. L. Tolman
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 34-53
Plenary Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27637
Articles are hosted by Taylor and Francis Online.
The primary objective of the U.S. Department of Energy Three Mile Island Unit 2 (TMI-2) research program, conducted by the EG&G Idaho TMI-2 Accident Evaluation Program, is to develop a comprehensive and consistent understanding of the TMI-2 accident. The accident scenario developed from this research is presented, including information relative to (a) the progression of core damage leading to a consolidated region of partially molten core material, (b) continued heatup of this consolidated region leading to extensive melting of the core, (c) failure of the supporting crust encasing the molten core material and relocation of 15 to 20 tonnes of molten core material into upper and lower core support assemblies and the lower plenum, and (d) interaction of molten core material with coolant and support structures in the lower plenum. Fission product release from fuel during the accident is also discussed.
