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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
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.
