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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.
P. Schira, E. Hutter
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 608-613
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-A25201
Articles are hosted by Taylor and Francis Online.
20 g of uranium powder was used in a laboratory setup at temperatures between 500 and 900 °C to study the retention of 1% each of O2, N2, NH3, CO2, and CH4 either as single impurities or three-component mixtures in H2. O2, NH3, and N2 as single impurities can be retained down to residual concentrations of 1 to 20 ppm at 500 °C. This is also true of CO2, but a large volume of CH4 is produced in this case. CH4 as a single impurity is not retained effectively below 900 °C. O2 redecomposes the uranium nitrides and carbides already formed. The achievable degrees of conversion are between 10% and 100 % for the reactions and increase as the temperature is raised.