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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.
J. Novak, Ian J. Hastings, Elio Mizzan, Real J. Chenier
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 254-265
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33285
Articles are hosted by Taylor and Francis Online.
Irradiated UO2 fuel elements with and without deliberately induced 0.8-mm-diam defects were heated in air at 220, 230, and 250°C for times up to 685 h. Pretest burnup was typically 190 MW·h/kg U (7600 MW·d/TeU) at a maximum linear power of 45 kW/m; cooling times were 1 to 3 yr. In fuel elements with six defects, diametral increases in excess of 5% and sheath splitting occurred after ∼200 h at 250°C, consistent with oxidation to U3O8. There was a maximum 2% increase in elements with one defect at 250°C, but no change in an irradiated but undefected control. Dimensional increases in defected elements at 220 and 230°C were typically <1% for times in excess of 600 h, consistent with oxidation primarily to nonswelling U3O7. The rate of weight change at 230 and 250°C was up to 50 times greater in defected irradiated elements, compared with that for defected unirradiated elements. There was no significant effect of power history or cooling time in the elements studied.