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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. Chabot, J. Lecomte, C. Grumet, J. Sannier, DCAEA-SCECF-SECNAU
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 614-618
Tritium Processing | Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988) | doi.org/10.13182/FST88-A25202
Articles are hosted by Taylor and Francis Online.
The feasibility of a permeation process using a palladium-silver alloy membrane, to separate deuterium and tritium from fusion reactor gaseous wastes needs demonstration owing to poisoning effects of impurities. A parametric investigation of the poisoning by the most important expected gaseous impurities (CO, CO2 and CH4) is carried out with the loop PALLAS, in function of membrane temperature (100 to 450°C), H2 pressure (0.3 to 14 kPa) and impurity concentration (0.2 to 9.5 vol.%). The poisoning effect of CO is a concern for the process while CO2 and CH4 appear to have no practical effect on the permeation rate. Depending on CO concentration optimal operating temperatures of the membrane should lie between 250 and 375°C limits.