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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.
Nobuhiro Yamamuro, Kazuyuki Udagawa, Toshihiro Natsume
Nuclear Science and Engineering | Volume 96 | Number 3 | July 1987 | Pages 210-220
Technical Paper | doi.org/10.13182/NSE87-A16382
Articles are hosted by Taylor and Francis Online.
Capture cross sections and gamma-ray spectra for the neutron-induced reactions with mTa and 197Au have been calculated using the level density parameters derived from a new low-lying level fitting method in which the constant temperature partial level density formula and the spin-selected level cumulation were used. The gamma-ray profile functions, of the Brink-Axel type with an anomalous bump, were employed for both nuclei. The capture cross sections, spectra, and gamma-ray strength functions obtained in the present calculation agree well with the experimental ones.
