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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.
Om Pal Singh, P. Bhaskar Rao
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 411-416
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33693
Articles are hosted by Taylor and Francis Online.
The core disruptive accident (CDA) analysis of liquid-metal fast breeder reactors is often performed using the saturated vapor pressure equation of state for the fuel. However, during the transient heating of the fuel in a voided core in the disassembly phase of CDAs, the fuel vapor pressure buildup may lag behind the temperature rise and thus may lead to the delayed disassembly of the core and the consequent large energy release. The formulations for such transient vapor pressure buildup and the results on the dynamics of fuel vapor pressure during the transient heating and its influence on the thermal energy release in a CDA are presented. The energy release calculations have been performed by incorporating the present formalism in the disassembly analysis code VENUS-II. In view of the uncertainties in some of the physical parameters, a parametric study was conducted to evaluate the effects of such uncertainties in their values on the results. These results are discussed in detail.
