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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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.
R. L. Macklin, C. W. Alexander
Nuclear Science and Engineering | Volume 104 | Number 3 | March 1990 | Pages 258-270
Technical Paper | doi.org/10.13182/NSE90-A23724
Articles are hosted by Taylor and Francis Online.
Uranium-236 neutron absorption is measured as a function of neutron time of flight from 20 eV to 1 MeV. The neutron flux is monitored with a 6Li glass scintillator. Average cross sections from 3 keV to 1 MeV are derived. Estimated uncertainties are <5% below 600 keV and increase to 9.5% at 1 MeV. From 20-eV to 4.2-keV neutron energy, 293 resonance peaks are parameterized.
