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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.
Franz J. Erbacher, Klaus Wiehr
Nuclear Technology | Volume 80 | Number 1 | January 1988 | Pages 153-160
Technical Paper | Advanced Light Water Reactor / Fission Reactor | doi.org/10.13182/NT88-A35555
Articles are hosted by Taylor and Francis Online.
The work performed in the FLORESTAN program at the Karlsruhe Nuclear Research Center on the reflooding and deformation behavior of a tight-lattice fuel rod bundle in a loss-of-coolant accident of an advanced pressurized water reactor (APWR) is described. The present forced-feed reflooding tests in an extremely tight bundle with a pitch-to-diameter ratio p/d = 1.06 show a very different thermal-hydraulic behavior compared to a standard pressurized water reactor. Blind code predictions have shown that most thermal-hydraulic computer codes do not adequately predict the reflooding behavior of this type of bundle. Deformation tests on stainless steel cladding tubes have shown that those with integral helical fins limit the burst strains and have high potential for APWR fuel rod cladding.
