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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.
G. Walter, B. Leugers, F.Käppeler, Z. Y. Bao, G. Reffo, F. Fabbri
Nuclear Science and Engineering | Volume 93 | Number 4 | August 1986 | Pages 357-369
Technical Paper | doi.org/10.13182/NSE86-A18471
Articles are hosted by Taylor and Francis Online.
The neutron capture cross sections of the stable krypton isotopes were determined in the energy interval from 4 to 250 keV using a C6D6-detector system in conjunction with the time-of-flight technique. The energy resolution of the measurement was 4% at 20 keV and 6% at 100 keV, and the experimental uncertainties were typically 6 to 10%. The measurements were complemented by statistical model calculations of all krypton isotopes in the mass range 78 < A < 86 to also obtain reliable cross sections for the unstable nuclei 79,81,85Kr. These calculations were based on local systematics for all relevant parameters, and the results were estimated to show uncertainties of 20 to 25%. Maxwellian average cross sections were calculated for kT = 30keV.