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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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
Yumi Yaita1, Shigeru O'hira, Kenji Okuno
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1294-1298
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-A30589
Articles are hosted by Taylor and Francis Online.
Hydrogen retention property on isotropic graphite was studied by exposure with a high flux atomized D/T particles. From the analysis of thermal desorption spectra it is clarified that deuterium implanted to graphite existed in two different states, one was that in a trap site the other was that of C-D bond. The amount of deuterium retained in graphite was in proportion to a half power of total incident fluence and no saturation was observed up to 1026 atoms·m−2. The total hydrogen isotope retention in the sample exposed to atomized D/T particles with total incident fluence of 1025 – 1026 atoms·m−2 were in the range of 1 × 1022−4 × 1022 atoms·m−2.1Visiting researcher from Toshiba Co.
