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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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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Fusion Science and Technology
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.
M. E. Sawan, L. A. El-Guebaly
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2069-2074
Blanket Shield and Neutronic | doi.org/10.13182/FST92-A30026
Articles are hosted by Taylor and Francis Online.
An efficient organic cooled low activation ferritic steel first wall and shield has been designed for the D-3He power reactor ARIES-III. The inboard shield is 65 cm thick and provides adequate magnet protection. The steel structure has a peak end-of-life damage of only 63 dpa and is expected to last for the whole reactor life. The total absorbed dose rate in the organic coolant is 1026 eV/s resulting in a radiolytic decomposition rate of 171 kg/hr. Tritium production leads to a release rate of 33.5 Ci/d and an acceptable off-site effluent dose < 1.3 mrem/yr.