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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.
J. Voignier, S. Joly, G. Grenier
Nuclear Science and Engineering | Volume 112 | Number 1 | September 1992 | Pages 87-94
Technical Notes | doi.org/10.13182/NSE91-92N
Articles are hosted by Taylor and Francis Online.
Absolute neutron capture cross sections for natural elements of scandium, titanium, rubidium, molybdenum, iodine, cesium, cerium, praseodymium, holmium, lutetium, and gold, and separated isotopes of 190Os, 192Os, 194Pt, and 238U are measured in the 0.5- to 3.0-MeV energy range. For most of these nuclides and isotopes, experimental data are scarce and discrepant, especially for rubidium, 133Cs, cerium, lutetium, and 194Pt, where no data are available above 0.6 MeV. Gamma-ray spectra emitted in the capture of 0.5-MeV neutrons, as well as the multiplicity of the gamma-ray transitions, are presented.