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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.
Yassin A. Hassan
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 257-267
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33609
Articles are hosted by Taylor and Francis Online.
Three-dimensional fluid and thermal mixing analysis of a full-scale cold leg and downcomer of a Babcock & Wilcox-designed pressurized water reactor is performed. The impetus of the present study is to provide an accurate estimation of the local fluid temperatures in the cold leg and downcomer when the cold high-pressure safety fluid is injected into the cold leg carrying a hot fluid. Such temperature predictions are needed in resolving the so-called pressurized thermal shock issue in the nuclear industry. The unique feature of this study is the use of the accurate mass-flow-weighted skew-upwind scheme to approximate the convective transport terms in the COMMIX-1A code approximation of the fluid energy equation. This new scheme is shown to considerably reduce the false diffusion that plagued multidimensional thermal-hydraulic applications. The computed fluid velocity patterns and temperature predictions have shown similar behavior to the flow visualization and temperature field measurements in scaled experiments.