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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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July 2025
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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
Taichi Matsumura, Ryuji Nagaishi, Jun-ichi Katakura, Masahide Suzuki
Nuclear Science and Engineering | Volume 192 | Number 1 | October 2018 | Pages 70-79
Technical Paper | doi.org/10.1080/00295639.2018.1493856
Articles are hosted by Taylor and Francis Online.
In order to evaluate three-dimensional distributions of radionuclides with high precision from gamma-scanning profiles of adsorption vessels used for decontamination of radioactive water performed at severe accidents, gamma scanning of the submerged demineralizer system vessel at the Three Mile Island Unit 2 (TMI-2) accident was simulated in the axial and radial directions of real and cylindrical-shaped vessels using a Monte Carlo calculation code [Particle and Heavy Ion Transport Code System (PHITS)].
In the axial simulation, the true distribution of radioactive 137Cs in the zeolite packed bed of the vessel was successfully evaluated when a correction function derived from a virtual constant distribution of 137Cs was applied to the reported gamma-scanning profile. In the radial simulation, the virtual disk-formed and shell-formed sources of 137Cs displaced in the packed bed were clearly observed from the top and bottom views of the vessel. This new radial gamma scanning indicates that the radial localization of 137Cs could be well observed by measuring the gamma ray from the top view of the vessel during storage. Further, the radial gamma scanning from the side view and whether or not the radial localization of 137Cs can be confirmed in the normally existing gamma-scanning room were examined.
