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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. G. Clemmer, R. F. Malecha, I. T. Dudley
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 83-92
Tritium | doi.org/10.13182/FST83-A22849
Articles are hosted by Taylor and Francis Online.
The TRIO-01 experiment is a comprehensive test of in-situ tritium recovery from a miniaturized solid breeder blanket assembly. Other solid breeder blanket performance factors such as thermal hydraulics, tritium permeation, and gas phase chemistry will be tested as well. The capsule assembly is irradiated in the A2 core position of the Oak Ridge Research Reactor (ORR). Tritium release and recovery is tested by passing a He sweep gas through the solid breeder capsule measuring and collecting the tritium in the sweep stream. The TRIO-01 experiment has extensive on-line monitoring including sweep gas analysis, temperatures, neutron flux, and tritium permeation.