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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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.
Hidemasa Kato, Tohru Haga, Shigeru Ohteru, Hiroshi Kamikawa
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 361-380
Technical Paper | doi.org/10.13182/NSE84-A18505
Articles are hosted by Taylor and Francis Online.
A core management analysis of a 165-MW(electric) plutonium-uranium mixed-oxide-fueled heavy water reactor, Fugen, has been carried out and compared with some of the operational data through the initial cycle and three reload cycles. During these burnup cycles, the Fugen reactor has experienced refueling of 72 plutonium-uranium fuel bundles and 76 UO2 fuel bundles, including four special bundles for irradiating test samples. The core burnup, thermal flux distribution, power distribution, coolant flow distribution, etc., were calculated and compared with measurements. The root-mean-square (rms) error of the calculated thermal flux over the three-dimensional spatial nodes was found to be ∼3% for various core conditions, and the rms error of the calculated core flow distribution was within 2%. The reload patterns have been chosen in such a way that mixed oxide and UO2 fuel bundles can exist in a mixed bed loading with no attendant reactor control problems.
