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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.
Yoshiyuki Kataoka, Hiroaki Suzuki, Michio Murase, Isao Sumida, Tetsuo Horiuchi, Minoru Miki
Nuclear Technology | Volume 82 | Number 2 | August 1988 | Pages 147-156
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34103
Articles are hosted by Taylor and Francis Online.
A natural circulation boiling water reactor (BWR) with a rated capacity of 600 MW(electric) has been conceptually designed for small- and medium-sized light water reactors. The components and systems in the reactor are simplified by eliminating pumped recirculation systems and pumped emergency core cooling systems. Consequently, the volume of the reactor building is ∼50% of that for current BWRs with the same rated capacity; the construction period is also shorter. Its thermal-hydraulic characteristics, critical power ratio (CPR) and flow stability at steady state, decrease in the minimum CPR (ΔMCPR) at transients, and the two-phase mixture level in the reactor pressure vessel (RPV) during accidents are investigated. The 8 × 8 fuel bundles with 3.1-m active lengths are used to achieve high seismic resistance and good thermal-hydraulic characteristics. Operation pressure of 7.0 MPa and volumetric power density of 34.2 kW/ℓ are determined from the CPR and flow stability limitations. The maximum ΔMCPR appears at load rejection transient and is <0.05. The CPR under normal operation is >1.3, which is a sufficient margin for the limitation value of 1.12. The two-phase mixture level in the RPV during an accident does not decrease to lower than the top of the core; the core uncovery and heatup of fuel cladding would not occur during any loss-of-coolant accident.