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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, D. M. Drake, E. D. Arthur
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 98-119
Technical Paper | doi.org/10.13182/NSE83-A17717
Articles are hosted by Taylor and Francis Online.
Neutron capture cross sections of four stable tungsten isotopes were measured as a function of energy by time of flight at the Oak Ridge Electron Linear Accelerator. The resolution achieved, ΔE/E of at full-width at half-maximum, has allowed the analysis of several hundred resonance peaks at energies a few kiloelectron volts above the neutron binding energy. Strength functions were fitted to the average cross sections up to ∼100 keV, and average cross sections were extended with less precision from 100 to 2000 keV. The capture cross section of natural tungsten was calculated from measurements for individual isotopes. Compound nucleus calculations have been made with deformed optical model parameters for comparison with experimental cross sections.