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May 31–June 3, 2026
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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.
Gordon E. Hansen, Ronald G. Palmer
Nuclear Science and Engineering | Volume 103 | Number 3 | November 1989 | Pages 237-246
Technical Paper | doi.org/10.13182/NSE89-A23674
Articles are hosted by Taylor and Francis Online.
Critical experiments have been performed on a mock-up of the compact nuclear power source (CNPS), a small reactor system designed to provide power at sites where fuel costs and logistics make fossil-fuel-powered systems less attractive. Although the program has been canceled, its unique physics characteristics make the CNPS a useful benchmark for medium-enriched uranium-graphite-moderated reactors. The physical design, details of the critical experiments, and the methods and results of the analysis are described. The discrepancies between calculations and experiments are such that, though further modeling work is necessary to delineate the causes, the beginning-of-life performance of the reactor was adequately predicted.