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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.
R. L. Macklin
Nuclear Science and Engineering | Volume 89 | Number 1 | January 1985 | Pages 79-86
Technical Paper | doi.org/10.13182/NSE85-A17885
Articles are hosted by Taylor and Francis Online.
Neutron capture measurements were made on a sample of fission product palladium at the Oak Ridge Electron Linear Accelerator time-of-flight facility. One hundred thirty resonance peaks were parameterized up to 3.5 keV and the average cross section from 3 to 600 keV was derived. The data exceed the ENDF/B-Vevaluation by ∼25% in the 3- to 300-keV range but drop steeply below it at higher energies where neutron inelastic-scattering competition becomes important. The Maxwellian average cross section for kT = 30 keV is calculated as 1.34 ± 0.06 b, and the dilute resonance capture integral as 108.1 ± 4.3 b.