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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. G. Alsmiller, Jr., J. Barish
Nuclear Science and Engineering | Volume 80 | Number 3 | March 1982 | Pages 448-452
Technical Note | doi.org/10.13182/NSE82-A19830
Articles are hosted by Taylor and Francis Online.
Multigroup cross sections (66 neutron groups and 21 gamma-ray groups) are described for neutron energies from thermal to 400 MeV. The elements considered are hydrogen, 10B, 11B, carbon, nitrogen, oxygen, sodium, magnesium, aluminum, silicon, sulfur, potassium, calcium, chromium, iron, nickel, tungsten, and lead. These cross sections are available from the Radiation Shielding Information Center of the Oak Ridge National Laboratory.
