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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.
J. Sáfár, L. Lakosi
Nuclear Science and Engineering | Volume 115 | Number 4 | December 1993 | Pages 297-299
Technical Paper | doi.org/10.13182/NSE93-A24059
Articles are hosted by Taylor and Francis Online.
The cross section of the 93Nb(γ, γ′)93mNb reaction is calculated in the 5- to 30-MeV gamma-energy region in the framework of a gamma-ray cascade model with open nucleon emission channels and including pre-equilibrium contribution. The resulting cross-section curve shows one pronounced peak at the neutron separation energy with an integral of 3.1 mb-MeV up to 12 MeV. Taking into consideration the pre-equilibrium gamma emission, a negligible contribution to the calculated excitation curve results at ∼18 MeV. The influence of gamma background on the response of 93Nb as a neutron fluence monitor is estimated for two practical cases.
