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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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
Senate EPW Committee to hold Nieh nomination hearing
Nieh
The Senate Environment and Public Works Committee will hold a nomination hearing Wednesday for Ho Nieh, President Donald Trump’s nominee to serve as commission at the Nuclear Regulatory Commission.
Trump nominated Nieh on July 30 to serve as NRC commissioner the remainder of a term that will expire June 30, 2029, as Nuclear NewsWire previously reported.
Nieh has been vice president of regulatory affairs at Southern Nuclear since 2021, though since June 2024 he has been at the Institute of Nuclear Power Operations as a loaned executive.
A return to the NRC: If confirmed by the Senate, Nieh would be returning to the NRC after three previous stints totaling nearly 20 years.
A. Bousbia Salah, S. C. Ceuca, R. Puragliesi, R. Mukin, A. Grahn, S. Kliem, J. Vlassenbroeck, H. Austregesilo
Nuclear Technology | Volume 203 | Number 3 | September 2018 | Pages 293-314
Technical Paper | doi.org/10.1080/00295450.2018.1461517
Articles are hosted by Taylor and Francis Online.
Advanced three-dimensional (3-D) computational tools are increasingly being used to simulate complex phenomena occurring during scenarios involving operational transients and accidents in nuclear power plants. Among these scenarios, one can mention the asymmetric coolant mixing under natural-circulation flow regimes. This issue motivated some detailed experimental investigations carried out within the Organisation for Economic Co-operation and Development/Nuclear Energy Agency PKL projects. The aim was not only to assess the mixing phenomenon in the reactor pressure vessel but also to provide experimental data for computer code validations and more specifically thermal-hydraulic system codes with 3-D capabilities. In the current study, the ROCOM/PKL-3 T2.3 experimental test is assessed using, on one hand, thermal-hydraulic system codes with 3-D capabilities and, on the other hand, computational fluid dynamics computational tools. The results emphasize the capabilities and the differences among the considered computational tools as well as their suitability for such purposes.