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May 31–June 3, 2026
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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.
David D. Clark, Carol G. Ouellet, J. Scott Berg
Nuclear Science and Engineering | Volume 110 | Number 4 | April 1992 | Pages 445-454
Technical Paper | doi.org/10.13182/NSE92-A23917
Articles are hosted by Taylor and Francis Online.
Two major parts of the design study for a cold source for the cold neutron beam facility under construction at the Cornell University 500-kW TRIG A reactor are presented. The reasons are discussed for choosing mesitylene as the cold moderator and for choosing conduction through copper rods between the source and a cryogenic refrigerator as the cooling method, the basic criteria for these choices being safety and simplicity of operation. Measurements of the neutron fluxes and nuclear heating rates at the proposed source location are reported. A description is provided of studies to optimize the size and shape of the cold source within the restrictions imposed by the limited available volume, the measured radiation levels, and the chosen materials using Monte Carlo simulation with a personal computer. It is concluded that mesitylene cooled by conduction through copper can provide a very satisfactory, safe, and simple cold source for an intermediate-power research reactor.