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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.
Siyu Yi, Zhouyu Liu, Kunpeng Wang, Wei Shen, Tiejun Zu, Liangzhi Cao, Hongchun Wu
Nuclear Science and Engineering | Volume 199 | Number 1 | April 2025 | Pages S73-S92
Research Article | doi.org/10.1080/00295639.2023.2296239
Articles are hosted by Taylor and Francis Online.
Fully ceramic microencapsulated fuels is a promising potential fuel for pressurized water reactors because of its inherent safety, but double heterogeneity (DH) brings challenges to the neutronic calculation. In this paper, the Hébert model is applied to the global-local resonance method to solve DH, in which the Dancoff factor obtained by the neutron current method is used to transform the coupled fuel pins in the reactor into multiple independent one-dimensional equivalent cylindrical fuel pins. Then, the Hébert model and the hyperfine group method are used to perform the resonance self-shielding calculation in these independent pins. The Sanchez-Pomraning method coupled with the Method of Characteristics (Sanchez-MOC) method is introduced to the two-dimensional/one-dimensional transport module to realize the subsequent whole-core DH transport calculations. The proposed method has been implemented in the high-fidelity neutronics code NECP-X and tested with a set of cases. The results show good agreement with the Monte Carlo reference values for the reactivity and self-shielding cross sections.