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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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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
Xiaohua Cao, Wende Shen, Jingping Wan, Huajin Tan, Yixiang Jiang, Benfu Yang
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 550-555
Tritium Processing | Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30460
Articles are hosted by Taylor and Francis Online.
The first Chinese in-situ tritium release experiment is being carried out in the fission reactor SPRR-300 in the Southwest Institute of Nuclear Physics and Chemistry (SWINPC). Several runs of the experiment were conducted to study tritium generation and release behaviors from China-made γ-LiAlO2 pellets. The effects of some key operational factors (temperature, sweep gas composition and flow rate) upon tritium release were studied. The results show that the equilibrium tritium release rate at different temperatures approached the tritium generation rate obtained from neutron calculations. The tritium concentration in the sweep gas decreased with increasing the flow rate. Addition of a small quantity of hydrogen greatly enhanced the release of tritium. It was also found that the tritium released in the sweep gas was mostly in the form of HT. However, when the generated tritium was not purged in time, the HTO fraction increased gradually. By using the inventory difference method, through the special run which lasted 72 hours, we determined the diffusion coefficient for tritium in γ-LiAlO2. The obtained diffusivity and its activation energy were compared with those from other experiments. It was found that the value of Q was close to those from LILA and TTTEx experiments, but the value of D0 was smaller.
