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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
M. F. Smith, R. D. Watson, J. B. Whitley, J. M. McDonald
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 1174-1183
Beryllium Technology | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A39927
Articles are hosted by Taylor and Francis Online.
Materials testing of S-65-B grade beryllium has been conducted in order to evaluate the use of this material for limiter surfaces in the ISX-B and JET tokamaks. Selected thermal and mechanical properties were measured at temperatures up to 700 °C. These measurements revealed that S-65-B has exceptionally high ductility (up to roughly 50% elongation) at temperatures expected in normal operation of a beryllium limiter. Thermal fatigue tests under conditions relevant to limiters in ISX-B and JET were also performed using the Sandia National Laboratories Electron Beam Test System (EBTS). Results from these tests were compared to calculated results based on elastic-plastic finite element stress analyses. It was concluded from these tests and analyses that properly designed beryllium limiters should survive normal operation in ISX-B, JET, and similar devices without serious structural failure. Some degree of surface cracking can be expected, however, unless cyclic plastic deformation at the heated surfaces can be adequately controlled by careful design of the limiter.