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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.
W. L. Filippone, M. S. Smith,S. Woolf, J. C. Garth
Nuclear Science and Engineering | Volume 95 | Number 1 | January 1987 | Pages 22-46
Technical Paper | doi.org/10.13182/NSE87-A20430
Articles are hosted by Taylor and Francis Online.
An electron transport solver has been developed based on a streaming ray (SR) solution to the Spencer-Lewis equation. Several special numerical techniques were used to make the algorithm fast and accurate. These include,an efficient routine for simulating energy loss straggling,use of extended-transport-corrected and Fokker-Planck equivalent cross sections, which speed convergence and reduce both angular and spatial differencing errors,a discrete transport correction, which further speeds convergence and further reduces spatial differencing errors,the method of numerical shoves and countershoves, which attempts to estimate and correct the remaining spatial differencing errors.The extended transport correction and the Fokker-Planck equivalent cross sections were originally developed for SN computations. The remaining techniques are new. The use of all these techniques together with the SR method has led to a complicated but highly efficient electron transport algorithm. Its efficiency is especially evident in energy spectrum calculations for which other fast algorithms such as the SN method often yield poor results. Several sample calculations involving electron transport in aluminum slabs are presented.