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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. W. Moir, J. D. Lee, M. S. Coops, F. J. Fulton, W. S. Neef, Jr., D. H. Berwald, R. B. Campbell, B. Flanders, J. K. Garner, N. Ghoniem (Consultant, UCLA), J. Ogren, Y. Saito, A. Slomovik, R. H. Whitley, K. R. Schultz, G. E. Benedict, E. T. Cheng, R. L. Creedon I. Maya, V. H. Pierce, J. B. Strand, C. P. C. Wong, J. S. Karbowski, R. P. Rose, J. H. Devan, P. Tortorelli, L. G. Miller, P. Y. S. Hsu, J. M. Beeston, N. J. Hoffman, D. L. Jassby
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 589-598
Fusion System Studies | doi.org/10.13182/FST4-2P2-589
Articles are hosted by Taylor and Francis Online.
Studies of the technical and economic feasibility of producing fissile fuel in tandem mirrors and in tokamaks for use in fission reactors are presented. Fission-suppressed fusion breeders promise unusually good safety features and can provide make-up fuel for 11 to 18 LWRs of equal nuclear power depending on the fuel cycle. The increased revenues from sales of both electricity and fissile material might allow the commercial application of fusion technology significantly earlier than would be possible with electricity production from fusion alone. Fast-fission designs might allow a fusion reactor with a smaller fusion power and a lower Q value to be economical and thus make this application of fusion even earlier. A demonstration reactor with a fusion power of 400 MW could produce 600 kg of fissile material per year at a capacity factor of 50%. The critical issues, for which small scale experiments are either being carried out or planned, are: 1) material compatibility, 2) beryllium feasibility, 3) MHD effects, and 4) pyrochemical reprocessing.