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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
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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Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
Take steps on SNF and HLW disposal
Matt Bowen
With a new administration and Congress, it is time once again to ponder what will happen—if anything—on U.S. spent nuclear fuel and high-level waste management policy over the next few years. One element of the forthcoming discussion seems clear: The executive and legislative branches are eager to talk about recycling commercial SNF. Whatever the merits of doing so, it does not obviate the need for one or more facilities for disposal of remaining long-lived radionuclides. For that reason, making progress on U.S. disposal capabilities remains urgent, lest the associated radionuclide inventories simply be left for future generations to deal with.
In March, Rick Perry, who was secretary of energy during President Trump’s first administration, observed that during his tenure at the Department of Energy it became clear to him that any plan to move SNF “required some practical consent of the receiving state and local community.”1
M. S. Kazimi, J. C. Chen
Nuclear Technology | Volume 38 | Number 3 | May 1978 | Pages 339-366
Critical Review | doi.org/10.13182/NT78-A32033
Articles are hosted by Taylor and Francis Online.
The analyses performed to evaluate the capacity to contain the core materials after a hypothetical core meltdown accident are generally grouped under the area of post-accident heat removal (PAHR). Substantial advancement in the state-of-the-art of the PAHR area has occurred within the last few years. The key issues of PAHR, as applied to safety analyses of liquid-metal breeder reactors, are summarized in this Review. The Review includes heat source strength for post-accident conditions, in-vessel core debris retention, ex-vessel core debris retention, and the effects of alternative fuel materials.
