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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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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.
Donald L. Smith
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 109-114
Technical Note | doi.org/10.13182/NSE79-A21294
Articles are hosted by Taylor and Francis Online.
Cross-section ratios for production of 0.843-, 1.013-, and 2.209-MeV gamma rays at 55 deg by the 27Al(n,n′γ)27Al reaction relative to fast-neutron fission of 235U have been measured at intervals of ∼0.05 MeV from threshold up to ∼2.5 MeV, with an average neutron energy resolution of ∼0.08 MeV. These ratios and ENDF/B-IV fission cross sections were used to compute gamma-ray production cross sections. Gamma-ray angular distributions were measured at En = 1.112, 1.310, 1.512, 1.714, 1.914, 2.118, 2.310, and 2.512 MeV. These distributions were found to be isotropic within the experimental errors. The experimental results are compared with data from the literature and with results from optical/statistical model calculations of neutron inelastic scattering from aluminum.
