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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
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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.
Minsuk Seo
Nuclear Technology | Volume 207 | Number 12 | December 2021 | Pages 1902-1912
Technical Paper | doi.org/10.1080/00295450.2020.1860614
Articles are hosted by Taylor and Francis Online.
Ensuring the thermal stability of heat-generating nuclear waste glass canisters in interim storage and the thermal stability of bentonite in the deep geological repository are crucial to preserving the function of the waste form. Yet thermal stability might be challenged by further heated air conditions and excessive heat load in the waste form, such that the maximum temperature would be higher than the glass transition temperature undesirably. The finite element method was carried out for the n × n × 4 (n = 1, 3, 5) multicanister system for the sake of predicting the maximum temperatures of interim storage. The internal heat source amount and exiting air temperature of the system were varied to see different storage environments. The maximum heat load of a 15.8 kW/m3 canister was in a safe range (glass transition temperature of 500°C), whereas an 18.6 kW/m3 canister was not. There is a possibility to extend thermal stability to a system larger than n = 5 for 15.8 kW/m3 based on the converging maximum temperature trends. Besides, the maximum temperature of the canister and bentonite clay in a deep geological repository is potentially below the thermal criterion if the canister cools down for about 65 to 70 years.