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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.
C. A. Ciarcia, G. P. Couchell, J. J. Egan, G. H. R. Kegel, S. Q. Li, A. Mittler, D. J. Pullen, W. A. Schier, J. Q. Shao
Nuclear Science and Engineering | Volume 91 | Number 4 | December 1985 | Pages 428-443
Technical Paper | doi.org/10.13182/NSE85-A18359
Articles are hosted by Taylor and Francis Online.
Fast neutron inelastic scattering cross sections for levels between 700- and 1400-keV excitation energy in 232Th have been measured using the (n,n′) time-of-flight (TOF) technique. Measurements of 125-deg differential cross sections were made using neutrons with a typical energy spread of 8 to 10 keV, generated by the 7Li(p,n)7Be reaction. The incident neutron energies covered three regions: (a) 950 to 1550 keV in 50-keV intervals with the TOF spectrometer optimized to detect 200- to 600-keV scattered neutrons, (b) 1200 to 2000 keV in 100-keV intervals with the spectrometer optimized to detect 400- to 800-keV scattered neutrons, and (c) 1700 to 2100 keV in 100-keV steps with the spectrometer optimized for 800- to 1300-keV scattered neutrons. Throughout the experiment, an overall energy resolution of < 15 keV was maintained. Level cross sections were deduced from the 125-deg differential scattering cross sections and are compared with (n,n′λ) measurements and the ENDF/B-V evaluation. Angular distributions for states in the 700- to 900- keV region have been measured at 1.2, 1.5, and 2.0 MeV.