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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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
V.L. Arbuzov, V. B. Vykhodets, G. A. Raspopova
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1127-1131
Tritium Properties and Interaction with Material | 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-A30558
Articles are hosted by Taylor and Francis Online.
The interaction of radiation-induced defects with deuterium atoms at room tenperature was studied for commercial vanadium, V-H and V-D alloys. During a 700 keV D+ bombardment the accumulation of D in the irradiated area was measured by means of NRA using the reaction D(d,p)T. It was shown that in the irradiated area of the V-D alloys (0.01–0.1 at .% D) the D concentration depends on both the fluence and the alloy composition. As the fluence is increased, the accumulated amount saturates. The saturation level depends on the D concentration and is 3 to 6 times as high as the D concentration in the bulk. The D segregation is due to the formation of immobile or low-mobile “D atom — radiation defect” conplexes. At the same time free D atoms are almost immediately redistributed in the bulk of the sample. A complex deuterium-protium segregation in V-D and V-H alloys under D+ bombardment was studied too. The accumulation of implanted deuterium in the irradiation-damaged area was examined for alloys with a high (0.6–2.65 at .% H) content of 1H hydrogen isotope. It is shown that the implant accumulation level is indepedent of the bombardment dose but is determined by the content of “free” protium in the alloys: the higher the protium concentration, the lower the accumulation level.
