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Division Spotlight
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.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Fusion Science and Technology
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.
R. M. Hunt, M. Narula, M. A. Ulrickson, T. T. Martin, A. Ying
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 38-42
ITER | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8872
Articles are hosted by Taylor and Francis Online.
Understanding the manner in which the First Wall Qualification Mockup (FWQM) responds structurally to simulated ITER conditions is important to the establishment of a reliable first wall. This paper provides a thermal and structural response analysis for the first round of qualification tests performed at Sandia National Laboratories. The results display the stresses and strains created in the FWQM as a result of the thermal expansion that occurred when subjected to cyclic heat flux under simulated ITER normal and MARFE conditions. From this structural response, further insight may be gained into the likelihood of fatigue failure of the Beryllium//CuCrZr interface once the first wall is in operation in ITER. While fully determining the reliability of this joint is beyond the scope of this study, some suggestions are made as to how this topic might be addressed with further research. Also investigated are the thermal patterns seen during testing that indicated slight variation from the intended test parameters. It is shown that these disparities from the ideal test parameters do not significantly affect the qualification of the FWQM.
