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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.
K. Shure
Nuclear Science and Engineering | Volume 85 | Number 1 | September 1983 | Pages 51-55
Technical Note | doi.org/10.13182/NSE83-A17151
Articles are hosted by Taylor and Francis Online.
The contributions from actinides to the decay heat and the decay rate relative to those from fission products in highly irradiated 235U-enriched uranium has been assessed. This assessment, which is based on measured and associated calculated actinide concentrations in a sample of uranium in which the 235U had been burned to 17% of its original >97% content (i.e., to ∼17% 235U), indicates that for most practical times (<108 s) after reactor shutdown, the actinide contribution to the decay heat and to the decay rate is a reasonably small fraction (<7%) of the total and comes mainly from 237U, 238Np, and 238Pu. These results differ from those for uranium only slightly enriched in 235U.