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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.
L. W. Weston, J. H. Todd
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 248-259
Technical Paper | doi.org/10.13182/NSE83-A17793
Articles are hosted by Taylor and Francis Online.
The ratios of the neutron fission cross sections σf(240Pu)/σf(239Pu), σf(240Pu)/σf(235U), and σf(239Pu)/σf(235U) have been measured simultaneously with a multiplate ionization fission chamber using the Oak Ridge Electron Linear Accelerator as a neutron source over the neutron energy range from 5 keV to 20 MeV. The 240Pu ratio data are in overall agreement with ENDF/B-V with exceptions in relatively narrow neutron energy regions. Below 150 keV and from 10 to 20 MeV, the present 239Pu/235U fission ratios indicate significant discrepancies when compared to ENDF/B-V. These ratios are important for thermal and fast reactor applications.
