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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.
Shigeyasu Sakamoto, Eiping Quang, Glenn F. Knoll
Nuclear Science and Engineering | Volume 109 | Number 2 | October 1991 | Pages 215-220
Technical Note | doi.org/10.13182/NSE91-A28519
Articles are hosted by Taylor and Francis Online.
Neutron capture cross sections for the 197Au(n, γ)198Au reaction have been absolutely determined at neutron energies of 23 and 967 keV. These are the median energies of the two photoneutron sources, Sb-Be and Na-Be, applied in this study. Reaction rates were determined by gamma counting of the 198Au activity using a pair of cylindrical NaI(Tl) detectors. The detection efficiency of the detectors was determined using 4π beta-gamma coincidence counting techniques. The neutron emission rates of the photoneutron sources were determined by indirect comparison with the U.S. National Bureau of Standards NBS-I neutron standard source using the University of Michigan manganese bath. The values obtained for the 197Au(n,γ)198Au cross section are 617.8 ± 11.1 mb and 99.7 ± 2.8 mb at 23 and 967 keV, respectively.
