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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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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.
J. C. Courtney, K. R. Ferguson, J. P. Bacca
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 30-41
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A16199
Articles are hosted by Taylor and Francis Online.
The Hot Fuel Examination Facility/South, located at the Idaho National Engineering Laboratory, supports the nation’s nuclear energy program by providing a facility for destructive and nondestructive testing of reactor fuels and materials. Irradiated subassemblies and test devices are transferred from the adjacent Experimental Breeder Reactor II or other irradiation facilities into the hot cells. The reliability of those systems required to inhibit the release of radioactivity to the environment is reviewed, and the operations at the facility are described. For each of two hypothetical accidents, release fractions were developed for noble gases, iodines, cesiums, and particulate radionuclides based on realistic but conservative data. The methodologies of the International Commission on Radiological Protection (ICRP)— both ICRP-2 and ICRP-30—were used to determine the radiological consequences at off-site receptors. By either technique, dose commitments from inhalation and submersion were small fractions of current federal guidelines. The relative contribution of each radionuclide was determined; iodine and cesium were more significant than plutonium for the decay times considered.