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Division Spotlight
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.
Meeting Spotlight
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
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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Nuclear Science and Engineering
November 2021
Nuclear Technology
Fusion Science and Technology
August 2021
Latest News
Hanford completes wastewater basin work to support tank waste treatment
Record-breaking heat and the vast size of the job did not stop the Department of Energy’s Office of River Protection and its tank operations contractor, Washington River Protection Solutions (WRPS), from completing a construction project critical to the Hanford Site’s Direct-Feed Low-Activity Waste program for treating radioactive tank waste.
H. H. Toudeshki, C. J. Martin, F. Najmabadi, J. P. Blanchard
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 535-540
Technical Paper | Proceedings of TOFE-2014 | dx.doi.org/10.13182/FST15-112
Articles are hosted by Taylor and Francis Online.
ARIES ACT-1 is a conceptual design for a commercial tokamak with aggressive physics and engineering. In the spirit of advanced engineering, the vacuum vessel design employed several novel concepts. It eliminates the use of water cooling in order to allow higher temperature operation and reduce the tritium inventory. It employs a low activation bainitic steel that eliminates the need for post-weld heat treatment. It includes sufficient volume to accommodate a full loss of coolant accident. Finally, it employs a novel mechanical design in order to withstand the operating stresses during normal operation, anticipated transients, and disruptions. In this paper, we present the most recent design for this component, update the stress analysis confirming the suitability of the design, and present results for disruption forces due to a plasma quench.
