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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.
Kazuichiro Hashimoto, Kunihisa Soda, Hideo Sekiya
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 1058-1066
Late Paper | TMI-2: Decontamination and Waste Management / Nuclear Safety | doi.org/10.13182/NT89-A27697
Articles are hosted by Taylor and Francis Online.
A thermal-hydraulic analysis of the initial 174 min of the Three Mile Island Unit 2 (TMI-2) accident was performed using the THALES (Thermal-Hydraulic Analysis of Loss-of-Coolant, Emergency Core Cooling and Severe Core Damage)-PM1/TMI code. The purpose of the analysis was to verify whether the THALESPMl/TMI code is capable of describing an accident progression in an actual plant. The initial and boundary conditions were based on the TMI-2 Standard Problem data base that was used by the Organization for Economic Cooperation and Development/Nuclear Energy Agency Committee on the Safety of Nuclear Installations in performing the TMI-2 Analysis Exercise. The analytical results generally agree with the actual behavior, indicating that the physical models employed in the code are reasonable. Better results were obtained using this analysis concerning the core degradation behavior in the early phase of the transient in which the debris node was assumed to remain at the original location. However, the physical models for the fuel relocation and debris formation need further improvement to be consistent with accident progression in the later phases of the transient.