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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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
Yuki Edao, Satoshi Fukada, Hidetaka Noguchi, Akio Sagara
Fusion Science and Technology | Volume 55 | Number 2 | February 2009 | Pages 140-151
Technical Paper | doi.org/10.13182/FST09-A4067
Articles are hosted by Taylor and Francis Online.
The rate of tritium released from temperature-controlled Flibe (a mixed molten salt of 2LiF + BeF2) after neutron irradiation was determined comparatively under two different conditions of Ar-H2 (10%) or Ar gas purge at a constant or linearly elevated temperature. Experimental rates of tritium release were analyzed based on its diffusion in Flibe and isotopic exchange between T atoms on surfaces and H atoms included in gaseous components. Gas released from Flibe had compositions of various ratios of HT to TF depending on the different conditions of Ar-H2 or Ar purge gas. The major molecular species of tritium released from Flibe after neutron irradiation was HT under the condition of the Ar-H2 purge and 300°C. The rate of tritium release under the Ar-H2 purge was simulated well by the present analytical model. Although its chemical form immediately after the release was TF under the condition of Ar purge, it was changed to HT partly by interaction with metallic surfaces.