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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 111 | Number 4 | August 1992 | Pages 415-421
Technical Paper | doi.org/10.13182/NSE92-A15488
Articles are hosted by Taylor and Francis Online.
The fission cross sections of 235U and 239Pu are measured with very high neutron energy resolution (0.17 ns/m) in the energy region from 100 to 2000 eV for 235U and to 20000 eV for 239Pu. The purpose of this measurement is to provide fission cross sections with energy resolution comparable with that available from transmission measurements for the purpose of deriving multilevel resolved resonance parameters. Fission ion chambers are used to detect fission fragments, and a 10B ionization chamber is used to measure the relative neutron flux at the 86-m flight path of the Oak Ridge Electron Linear Accelerator. The measured fission cross sections are the highest resolution measurements of good accuracy reported in the neutron energy range above 400 eV.