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May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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. Sanchez, N. J. McCormick
Nuclear Science and Engineering | Volume 83 | Number 1 | January 1983 | Pages 63-71
Technical Paper | doi.org/10.13182/NSE83-A17989
Articles are hosted by Taylor and Francis Online.
Direct and adjoint plane geometry diffusion solutions are combined to provide an inverse method for determining multigroup cross sections and diffusion coefficients; for the equations to work, one group constant for each group must be known. The equations are linear and independent of the slab thickness and require that only the fluxes on the boundaries be measured for a set of experiments with known ingoing currents. The accuracy of the method has been numerically checked using analytical solutions. Another application of the method is to determine the relative concentration of one or more isotopes in a mixture of isotopes whose microscopic cross sections are known.