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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.L. Carconi, S. Casadio, A. Moauro
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 775-780
Material Properties | doi.org/10.13182/FST92-A29842
Articles are hosted by Taylor and Francis Online.
Measurements of impurities and tritium releasing characteristics of Lithium Aluminate and Zirconate, prepared by ENEA in the frame of the European Program on Fusion Technology, have been performed, respectively, by neutron activation analysis (NAA) and “out of pile” annealing. The resulting tritium removing rate from the ceramics was interpreted in terms of surface desorption kinetics. With reference purge gas (He + 0.1% H2), the predominant form of tritium, released by lithium aluminate is HT/T2, HTO/T2O by lithium zirconate. The latter was found to have a better performance in tritium release than aluminate. The presence of moisture was found to catalyse the tritium release at lower temperatures.
