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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.
Toshikazu Shibata, Tadaharu Tamai, Masatoshi Hayashi, John C. Posey, James L. Snelgrove
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 405-417
Technical Paper | doi.org/10.13182/NSE84-A18507
Articles are hosted by Taylor and Francis Online.
Irradiated uranium-aluminide fuel plates of 40% 235U enrichment were heated for the determination of the amounts of fission products released at temperatures up to and higher than the melting point of the fuel cladding material. The release of fission products from the fuel plate at temperatures below 500°C was negligible. Three stages of fission product release were observed. The first rapid release was observed at ∼561°C along with blistering of the plates. The next release, which occurred at 585°C, might have been caused by melting of the Type 6061 aluminum alloy. The last release of fission product gases occurred at 650°C, which probably corresponds to the eutectic temperature of the uranium-aluminum alloy. The released material was mostly xenon, and small amounts of iodine and cesium were observed.