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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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Nuclear Science and Engineering
June 2025
Nuclear Technology
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May 2025
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.
Keiji Kobayashi, Junnosuke Horie, Keiji Kanda, Toshikazu Shibata
Nuclear Science and Engineering | Volume 71 | Number 2 | August 1979 | Pages 143-153
Technical Paper | doi.org/10.13182/NSE79-A20405
Articles are hosted by Taylor and Francis Online.
Measurement of the reactivity effect due to substitution of metallic thorium for the core elements in a critical assembly has been made as part of the preliminary experiment for an intermediate reactor by using the multiregion critical core. The results of criticality calculations have been in good agreement with experiments in the case of the core without thorium, although the calculated neutron multiplication factor has been ∼2% larger than the experimental value for the core with thorium.