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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.
Raphael Aronson
Nuclear Science and Engineering | Volume 86 | Number 2 | February 1984 | Pages 136-149
Technical Paper | doi.org/10.13182/NSE86-136
Articles are hosted by Taylor and Francis Online.
The results of high-order PN calculations for the one-speed albedo and Milne problems in spherical geometry are presented. The computations were performed by the transfer matrix approach. The analysis is included in the paper. Reflection probabilities are given for spheres of various radii and for the region exterior to spheres: reflection and transmission probabilities for spherical shells and extrapolation lengths for the exterior Milne problem. The method is found to diverge for sufficiently high values of N—the smaller the radius, the more rapidly divergence sets in. For moderate and large radii (≳2 mfp), the method nevertheless gives generally excellent results.