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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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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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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.
Masabumi Nishikawa, Kazuya Furuichi, Hiroki Takata
Fusion Science and Technology | Volume 50 | Number 4 | November 2006 | Pages 521-527
Technical Paper | doi.org/10.13182/FST06-A1275
Articles are hosted by Taylor and Francis Online.
Concrete walls play the role not only of the structural material but also of the final barrier of a multiconfinement system of tritium in a fusion reactor or a tritium-handling facility. Therefore, it is required that the behavior of tritium in the concrete materials be clarified to certify the radiation safety of a fusion reactor. The diffusion coefficient of hydrogen in cement paste is obtained by using the permeation experiment in this study, and it is found that the diffusion coefficient of hydrogen in the cement paste is only one order magnitude smaller than the diffusion coefficient of hydrogen in air. Calculation using the diffusion coefficient obtained in this study indicates that the gaseous tritium, HT or T2, can permeate rather rapidly to the outside through the concrete wall of a tritium-handling facility. This calculation implies that installation of a tritium recovery system with proper decontamination performance is required to minimize the tritium transfer to the outer environment.