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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.
S. Pearlstein
Nuclear Science and Engineering | Volume 83 | Number 2 | February 1983 | Pages 312-315
Technical Note | doi.org/10.13182/NSE83-A18224
Articles are hosted by Taylor and Francis Online.
Optical model parameters are recommended for the analysis of neutron cross sections in the atomic number range 24 to 73 and 4- to 20-MeV energy range. Using the real well potential V and real well radius coefficient R in the combination VR2, unique energy-independent fitting parameters are obtained regardless of the initial estimates. Neutron data for iron up to 100 MeV are analyzed using uniquely determined energy-dependent parameters.
