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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
DOE issues RFI for a spent fuel consolidated interim storage facility
The Department of Energy’s Office of Nuclear Energy has issued a request for information opportunity for the design and construction of a federal consolidated interim storage facility (CISF) for spent nuclear fuel. The DOE is planning on establishing a federal CISF to manage SNF until a permanent repository is available. In May, the DOE received initial approval, known as “Critical Decision-0,” for such a facility.
The deadline for submissions is September 5.
K. Tsuzuki, H. Kimura, Y. Kusama, M. Sato, H. Kawashima, K. Kamiya, K. Shinohara, H. Ogawa, K. Uehara, G. Kurita, S. Kasai, K. Hoshino, N. Isei, Y. Miura, M. Yamamoto, K. Kikuchi, T. Shibata, M. Bakhtiari, T. Hino, Y. Hirohata, Y. Yamauchi, K. Yamaguchi, H. Tsutsui, R. Shimada, H. Amemiya, Y. Nagashima, T. Ido, Y. Hamada
Fusion Science and Technology | Volume 49 | Number 2 | February 2006 | Pages 197-208
Technical Paper | JFT-2M Tokamak | doi.org/10.13182/FST06-A1095
Articles are hosted by Taylor and Francis Online.
Compatibility between plasma and reduced activation ferritic steel, which is the leading candidate for the structural material of a fusion demonstration reactor, has been investigated in the Advanced Material Tokamak EXperiment (AMTEX). Ferritic plates (FPs) were installed progressively in the JFT-2M tokamak. The effect of ferromagnetism on plasma production, control, confinement, and stability has been investigated. Impurity release behavior has also been investigated. Even when the inside vacuum vessel wall was fully covered with the FPs and the tokamak plasma was operated close to the wall, no deleterious effect was observed, and the normalized beta could be increased up to ~3.5. Thus, encouraging results are obtained for application of this material to the demonstration reactor.