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Division Spotlight
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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Donald L. Smith
Nuclear Science and Engineering | Volume 64 | Number 4 | December 1977 | Pages 897-901
Technical Note | doi.org/10.13182/NSE77-A14510
Articles are hosted by Taylor and Francis Online.
Cross-section ratios for production of 0.439-MeV gamma rays near 55 deg by the 23Na(n, n′y)23Na reaction relative to fast-neutron fission of 235U have been measured with an error of ±8% at intervals of 0.05 MeV from threshold up to ∼2 MeV, with an average neutron energy resolution of ∼0.07 MeV. Gamma-ray angular distributions were measured at En = 0.644, 0.793, 1.093, 1.245, 1.499, 1.799, and 2.044 MeV. The measured ratios and ENDF/B-IV fission cross sections were used to compute gamma-ray production cross sections. The experimental results are compared with data from the literature, and implications for liquid-metal fast breeder reactor technology are discussed.
