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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.
Tatsuo Izumida, Koji Kato, Fumio Kawamura, Hideo Yusa
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 249-253
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A33649
Articles are hosted by Taylor and Francis Online.
Alternating square-wave current electrolysis using a Na2SO4 electrolyte was studied as a removal method for radioactive contaminated oxidation film on metal surfaces. After the oxidation film was selectively removed using the Na2SO4 electrolyte, base metal was removed. Based on a diffusion model in which the removal rate of the surface oxidation film depends on the diffusion rates of O2- and Fe2+ ions in the film, the optimum cycle of the alternating square current was estimated to be 90 s (the square widths of the negative and positive currents were 60 and 30 s, respectively). The theoretical estimation was in good agreement with the experiment results. Using this decontamination method, decontamination factors of 101 to 104 were obtained for stainless steels of a boiling water reactor coolant system and radioactive simulated samples.
