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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
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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
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.
Richard D. Schauss, David K. Cowser, Michael J. Kelley
Nuclear Technology | Volume 87 | Number 3 | November 1989 | Pages 690-700
Technical Paper | TMI-2: Remote Technology and Engineering / Nuclear Safety | doi.org/10.13182/NT89-A27721
Articles are hosted by Taylor and Francis Online.
In February 1985, work was initiated to develop a three-dimensional computerized solids model of the Three Mile Island Unit 2 (TMI-2) reactor building (RB) systems and facilities. Although it was initially planned to use this model to support the acquisition of data for radiological characterization purposes, the unique ability of the solids modeling system to integrate plant configuration data into a single source made it an ideal tool for supporting various other TMI-2 recovery engineering activities as well. In addition to the RB model, a model of the auxiliary and fuel-handling buildings and a very detailed model of the TMI-2 reactor have also been developed. The application of the reactor model to support activities related to reactor vessel defueling and reactor components disassembly is the primary subject of this paper.