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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.
M. Caro, J. Ligou
Nuclear Science and Engineering | Volume 83 | Number 2 | February 1983 | Pages 242-252
Technical Paper | doi.org/10.13182/NSE83-A18217
Articles are hosted by Taylor and Francis Online.
Handling the highly anisotropic scattering of fast neutrons with conventional methods usually means that high-order Legendre expansions can be necessary to obtain correct angular fluxes. This drawback in standard transport calculations is avoided by applying the Boltzmann-Fokker-Planck (BFP) method, already used in transport of charged particles, to neutrons. Two methods are described to obtain the relevant input data for the one-dimensional BFP-1 code, one using basic differential scattering cross sections and the other using existing standard multigroup libraries. Numerical results for both methods are produced, revealing BFP as a powerful method when solving transport problems dealing with very fast neutrons. It is found that high accuracy, even for extreme cases of anisotropy, is achieved without increase of the computational effort.