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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.
H.Derrien, G. de Saussure, R. B. Perez
Nuclear Science and Engineering | Volume 106 | Number 4 | December 1990 | Pages 434-451
Technical Paper | doi.org/10.13182/NSE90-A23768
Articles are hosted by Taylor and Francis Online.
The results of an R matrix analysis of the 239Pu neutron cross sections up to 1000-eV neutron energy are reported. The analysis was performed with the multilevel multichannel Reich-Moore code SAMMY. The method of analysis is described, and the selection of experimental data is discussed. Some tabular and graphical comparisons between calculated and measured cross sections and transmissions are presented. The statistical properties of the resonance parameters are examined. The resonance parameters are proposed for the new evaluated data files ENDF/B-VI and JEF2.
