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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.
C. Don Fletcher, Mark A. Bolander
Nuclear Technology | Volume 81 | Number 1 | April 1988 | Pages 52-62
Technical Paper | Nuclear Safety | doi.org/10.13182/NT88-A34078
Articles are hosted by Taylor and Francis Online.
In Westinghouse four-loop pressurized water reactors (PWRs), many long small-diameter instrument tubes are employed to route flux monitoring instrumentation lines from the lower plenum of the reactor vessel to a flux mapping seal table. A recent safety concern is that a seismic event could hypothetically rupture instrument tubes at the seal table, effectively causing a lower plenum small-break loss-of-coolant accident (SBLOCA). Continued cooling of the reactor core during a SBLOCA requires depressurization of the primary coolant system such that emergency core cooling (ECC) injection flow balances the break flow. For a lower plenum SBLOCA, the break remains liquid-covered, thus retarding primary coolant system depressurization. As a result, for continued cooling of the core, the break must be sufficiently small such that ECC flow balances break flow at elevated pressures. This study investigates instrument tube ruptures at the seal table location. Separate effects analyses investigate instrument tube pressure and heat loss, instrument lines remaining within the tubes, and tube nodalization effects. Systems effects analyses evaluate the significance of the safety concern through a best-estimate, single-failure analysis for the Zion-1 PWR.