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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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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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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Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
August W. Cronenberg, E. L. Tolman
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 273-282
Technical Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27654
Articles are hosted by Taylor and Francis Online.
Inspection of the Three Mile Island Unit 2 (TMI-2) reactor vessel has yielded a wealth of information on core melt debris thermal interactions with vessel internal structures. The observed damage state of such structures is summarized and an analysis is presented to further the understanding of governing physical processes. Specifically, thermal damage is assessed for the baffle plates surrounding the core periphery, the core former plates, the bottom head instrument penetrations, and the lower head. Analysis indicates that differences in damage characteristics to such structures are due largely to differences in contact time with molten corium, the heat capacity of the various structures, and exposure to coolant. Vessel and debris examinations corroborate the present understanding of melt debris/structural interactions during the melt relocation phase of the TMI-2 accident.