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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.
A.M. Street, P.E. Hodgson
Nuclear Science and Engineering | Volume 92 | Number 3 | March 1986 | Pages 459-464
Technical Note | doi.org/10.13182/NSE86-A17533
Articles are hosted by Taylor and Francis Online.
The method previously used to analyze the inelastic scattering of neutrons by 238U by separating the cross sections into compound nucleus and direct interactions is applied to the corresponding data for 232Th. The fission and capture channels are now included explicitly, resulting in a 5% increase in the compound nucleus contribution. Other data and theoretical techniques are discussed briefly. The excitation functions for 24 states up to 2.5 MeV are analyzed, together with two angular distributions at 2.5 MeV.