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Human Factors, Instrumentation & Controls
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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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
W. Raskob
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 934-939
Tritium Safety | 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-A30525
Articles are hosted by Taylor and Francis Online.
In view of the public acceptance and the licensing procedure of projected fusion reactors, the release of tritium during normal operation as well as after accidents is a significant safety aspect. Tritium, being chemically identical to hydrogen and thus interacting directly with water and organic substances, differs considerably from the behaviour of other radionuclides in the environment. Therefore, the two consequence assessment codes UFOTRI and NORMTRI have been developed and applied to estimate the doses to the public from releases of tritium under accidental and routine conditions, respectively. In the frame of ITER (International Thermonuclear Experimental Reactor) and SEAFP (Safety and Environmental Aspects of Fusion Power) the dose/release translation has been determined for typical and various worst case release scenarios. Under worst case accidental release conditions, the dose/release translation for the early dose to an individual at the fence may range from 0.5 to 1 mSv/g HTO. The result for the EDE at the fence is up to 3 mSv/g HTO. The collective accidental dose/release translation is about 2.5 manSv/g HTO. However, due to processes inside the facility, only a small fraction of the mobilised activity may be released into the environment. Finally, the current status of the present assessment models is shortly analysed with regard to the strength and weakness of their approaches which led to the recommendation to concentrate on the plant physiological parts of the tritium codes.