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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. T. Santoro, R. G. Alsmiller, Jr., J. M. Barnes
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 449-459
Technical Paper | Blanket Engineering | doi.org/10.13182/FST91-A29385
Articles are hosted by Taylor and Francis Online.
Neutronics parameters including the source neutron spectrum, activation rates, and the tritium breeding in the Li2O test zone of the Fusion Neutron Source Phase II experiment performed at the Japan Atomic Energy Research Institute are calculated using the Monte Carlo code MORSE with ENDF/B-V transport and reaction cross sections. Favorable comparisons between the measured and calculated results are achieved for the 27Al(n,α), 58Ni(n,p), 93Nb(n,2n), and 197Au(n,2n) reactions. Calculated 58Ni(n,2n) and 197Au(n,γ) reactions do not agree with measured values within 10 to 40%. For the nickel reaction, the differences may be due to poor data in the ORACT files, while discrepancies for the gold data may be due to unknown quantities of hydrogen-rich epoxy used to coat the Li2CO3 blocks used in the test assembly walls. The calculated tritium breeding in the Li2O agrees with experimental values within ±10% for 6Li and ±15 to 20% for 7Li.