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May 31–June 3, 2026
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INL makes first fuel for Molten Chloride Reactor Experiment
Idaho National Laboratory has announced the creation of the first batch of enriched uranium chloride fuel salt for the Molten Chloride Reactor Experiment (MCRE). INL said that its fuel production team delivered the first fuel salt batch at the end of September, and it intends to produce four additional batches by March 2026. MCRE will require a total of 72–75 batches of fuel salt for the reactor to go critical.
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.