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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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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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Fusion Science and Technology
November 2024
Latest News
Texas-based WCS chosen to manage U.S.-generated mercury
A five-year, $17.8 million contract has been awarded to Waste Control Specialists for the long-term management and storage of elemental mercury, the Department of Energy’s Office of Environmental Management announced on November 21.
Igor Kupriyanov, Nikolay Porezanov, George Nikolaev, Liudmila Kurbatova, Vyacheslav Podkovyrov, Anatoly Muzichenko, Anatoly Zhitlukhin, Yury Gasparyan, Alexander Gervash
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 171-179
Technical Paper | doi.org/10.13182/FST13-749
Articles are hosted by Taylor and Francis Online.
Beryllium will be used as a plasma-facing material for the ITER first wall. It is expected that erosion of beryllium under transient plasma loads such as the edge-localized modes (ELMs) and disruptions will determine the lifetime of the ITER first wall. The results of recent experiments with the Russian beryllium of TGP-56FW ITER grade on the QSPA-Be plasma gun facility are presented. The Be/CuCrZr mock-ups were tested by deuterium plasma and radiative streams both with pulse duration of 0.5 ms and heat loads of 0.5 and 0.4 MJ/m2, correspondingly. Experiments were performed at 250 °C. The beryllium mock-ups were exposed to up to 100 shots. After 10, 40 and 100 shots, the evolution of surface microstructure and crack morphology were investigated as well as beryllium mass loss under the erosion process. The deuterium retention in erosion products was also studied by the thermal desorption method.