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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.
M. Sugimoto, P. T. Guenther, J. E. Lynn, A. B. Smith, J. F. Whalen
Nuclear Science and Engineering | Volume 103 | Number 1 | September 1989 | Pages 37-45
Technical Paper | doi.org/10.13182/NSE89-A23658
Articles are hosted by Taylor and Francis Online.
Neutron total cross sections of elemental beryllium are measured from 1 to 10 MeV with good precision. Differential neutron elastic scattering cross sections are measured from 4.5 to 10 MeV at intervals of ≈0.5 MeV and at ≈100 angular steps distributed between ≈18 and 160 deg at each incident energy. Concurrently, differential cross sections for the emission of a discrete inelastic neutron group corresponding to an excited level at (2.43 ± 0.06) MeV are determined over the same incident energy and angular range. Angle-integrated elastic scattering cross sections are deduced from the observed differential values to accuracies of ≈2.5%, and angle-integrated inelastic scattering cross sections to accuracies of ≈10%. The experimental results are compared with values given in ENDF/B-V, with attention to discrepancies and implications. Qualitative reaction mechanisms are suggested.