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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.
Sang Woon Shin, Hee Cheon No
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 378-383
Technical Paper | Material | doi.org/10.13182/NT86-A16079
Articles are hosted by Taylor and Francis Online.
To investigate the denting phenomenon, the rates of corrosion occurring in simulated tube/support plate crevices were examined by using seven model boilers at 1.11 MPa. The model boilers were operated with all-volatile treatment (morpholine + hydrazine) with 15- and 100-ppm chloride concentrations constituting 10% FeCl2, 30% NaCl, and 60% CaCl2. It was found that corrosion rates increased with heat flux. A model was proposed to explain this observation, based on mechanisms that acid chloride is concentrated in the tube/support plate crevices. The model is expressed by the following equation for empty heated crevices: Good agreement was obtained by comparing the results predicted by the model with Brown’s data and the present data for empty heated crevices, and with Pathania’s data obtained at high heat flux. Based on the above equation, a model was developed to describe chloride concentration within the crevices versus heat flux for given condenser leakage rates in nuclear steam generators. Results predicted by the model show that a small increase in condenser leakage rates gives a considerable increase in chloride concentration within the crevices.