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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. G. Glendinning, S. El-Kadi, C. E. Nelson, F. O. Pursert, C. R. Gould, L. W. Seagondollar
Nuclear Science and Engineering | Volume 82 | Number 4 | December 1982 | Pages 393-399
Technical Paper | doi.org/10.13182/NSE82-A21453
Articles are hosted by Taylor and Francis Online.
Differential cross sections are reported for elastic scattering of neutrons from 16O. Source neutrons were provided by the D(d,n)3He reaction with average neutron energies of 9.21, 9.71, 10.21, 10.70, 10.95, 11.15, 11.95, 12.45, 12.94, 13.94, and 14.93 MeV. Time-of-flight spectra were obtained for neutrons scattered by a BeO sample at 28 angles from 25 to 160 deg in 5-deg increments. Flight paths of 4 and 6 m were used. Spectra obtained with a separate beryllium sample were subtracted to remove the beryllium scattering contribution. The angular distribution data were corrected for finite source and finite sample-size effects. Legendre polynomial coefficients and total elastic scattering cross sections are reported for oxygen. The data are not well reproduced by the spherical optical model because of the many resonances in the total neutron cross section. Inclusion of resonances together with an optical model background improves the fits to the angular distribution and total cross-section data.