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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.
J. S. Gilmore, G. J. Russell, H. Robinson, R. E. Prael
Nuclear Science and Engineering | Volume 99 | Number 1 | May 1988 | Pages 41-52
Technical Paper | doi.org/10.13182/NSE88-A23544
Articles are hosted by Taylor and Francis Online.
Axial distributions of fissions and of fertile-to-fissile conversions in thick depleted uranium and thorium targets bombarded by 800-MeV protons have been measured. The amounts of 239Pu and 233 U produced were determined by measuring the yields of 239Np and 233Pa, respectively. The number of fissions was deduced from fission product mass-yield curves. Integration of the axial distributions gave the total number of conversions and fissions occurring in the targets. For the uranium target, experimental results were 5.90 ± 0.25 fissions and 3.81 ± 0.01 atoms of239Pu produced per incident proton. Corresponding calculated results were 6.14 ± 0.04 and 3.88 ± 0.03. In the thorium target, 1.56 ± 0.25 fissions and 1.25 ± 0.01 atoms of 233U per incident proton were measured; the calculated values were 1.54 ±0 0.01 fissions and 1.27 ± 0.01 atom/proton.