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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Kan Ashida, Masao Matsuyama, Kuniaki Watanabe
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 735-740
Tritium Properties and Interactions with Material | Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988) | doi.org/10.13182/FST88-A25222
Articles are hosted by Taylor and Francis Online.
Graphite is the primary candidate for the first wall of magnetically confined fusion devices. For this application, it is important to know the surface properties and trap/release behavior of hydrogen isotopes to understand fuel recycling/inventory in the graphite first wall. The surface analysis of as-received graphite revealed that the inherent hydrogen content is larger in isotropic compared to the anisotropic graphite. This is due to the presence of non-graphitized carbon atoms in the isotropic graphite which act as the trapping sites of hydrogen atoms. Ion bombardment causes the reduction of the crystallite size of graphite (damage modification), leading to amorphous-like structure. The thermal desorption spectra of hydrogen isotopes consisted of three desorption peaks for the modified graphite. The desorption mechanisms and parameters of three peaks are determined. These parameters were used to estimate the fuel inventory in the graphite.