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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.
Robert J. Wolfgang, Rayford L. Patterson
Nuclear Technology | Volume 87 | Number 3 | November 1989 | Pages 616-623
Technical Paper | TMI-2: Remote Technology and Engineering / Nuclear Safety | doi.org/10.13182/NT89-A27713
Articles are hosted by Taylor and Francis Online.
The 1979 Three Mile Island Unit 2 accident caused fuel particles (fines) and debris to be transported throughout the reactor coolant system (RCS). Estimates of the fuel quantities in the RCS outside the reactor vessel boundary (defined as ex-vessel areas) have been developed. These estimates, in conjunction with as-low-as-reasonably-achievable considerations, were used to determine which ex-vessel areas required defueling.
