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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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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
M. Okamoto, T. Nakano, M. Aida, M. Nomura, Y. Fujii, S. Sharafat
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1244-1249
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-A30580
Articles are hosted by Taylor and Francis Online.
Tritium permeation, particularly plasma driven permeation (PDP) through plasma facing materials has been identified as a critical safety issue for future fusion power devices. While PDP through metals has been reported earlier, this work presents the first measurements of permeation rates through SiC/SiC composite samples exposed to a modified RF-discharge plasma device. The response of the SiC/SiC composite samples to impinging plasma radiation was also investigated using SEM. In contrast to metals, SiC/SiC composite showed no evidence of PDP of deuterium. The SEMs revealed attack only of directly exposed fibers and fiber-matrix interfaces. In lieu of these measurements, SiC/SiC composites offer promising characteristics as plasma facing materials for future fusion devices.