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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
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.
Peter J. Jensen, V. K. Chexal, Jason Chao, William H. Layman
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 252-273
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34140
Articles are hosted by Taylor and Francis Online.
The Nuclear Safety Analysis Center (NSAC) at the Electric Power Research Institute has a Generic Safety Analysis Program to help resolve high-priority safety issues. Several high-priority safety issues considered at NSAC were resolved at least in part through the use of the RETRAN computer code. These issues are pressurized thermal shock, anticipated transients without scram in both pressurized and boiling water reactors, steam generator tube rupture, and scram frequency reduction.
