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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.
T. J. Dolan a, J. C. DeVeaux
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 1130-1135
Alternate Fuels and Innovative Confinement Concept | doi.org/10.13182/FST89-A39845
Articles are hosted by Taylor and Francis Online.
The DT fusion neutron yield is calculated as a function of plasma current I for a variety of cases, assuming that the plasma temperature scales as To = Tr(I/Ir)y(ar/a)x where subscripts r denote reference values, and x and y are scaling parameters. The first-wall minor radius a is limited by the tolerable heat flux q. If β = 15 %, R = 4 m, I = 10 MA, and q = 3 MW/m2, then a = 0.43 m, and the 14 MeV neutron current at the first wall is about 1018 neutrons/m2s. a Work begun at Phillips Research Center. On leave from the University of Missouri-Rolla.