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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.
Anton Bayer
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 217-227
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33720
Articles are hosted by Taylor and Francis Online.
As a continuation of the “German Risk Study: Phase A,” further plant-oriented analysis has been performed and the off-site accident consequence model has been partially improved. The plant-oriented analysis carried out at the Karlsruhe Nuclear Research Center has been focused on two release categories, namely FK2 (core meltdown followed by immediate release of radionuclides from the leaking containment) and FK6 (core meltdown followed by late release of radionuclides as a result of failure due to overpressure in the containment). The thermohydraulic processes in the molten mass and the behavior of the fission and activation products released from the molten mass are considered in a more realistic way. The improvements of the off-site accident consequence model relate mainly to a more realistic modeling of the deposition and resuspension processes, to the ingestion submodel, and to dose factors. The results show that the improvements of the off-site accident consequence model do not change the final results dramatically; the model rather draws a more realistic picture of the interrelated processes, and consequently allows the application of the model to other problems in the nuclear field as well. From the investigations belonging to the plant-oriented analysis it appears, however, that the releases to be expected from postulated accidents are remarkably lower. Consequently, the risk is lower than assessed in Phase A of this study.