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May 31–June 3, 2026
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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.
F. Corvi, G. Fioni, F. Gasperini, P. B. Smith
Nuclear Science and Engineering | Volume 107 | Number 3 | March 1991 | Pages 272-283
Technical Paper | doi.org/10.13182/NSE91-A23790
Articles are hosted by Taylor and Francis Online.
A set of efficiencies and response functions for 18 gamma rays in the range from 0.2 to 8.4 MeV has been experimentally determined via a (p,γ) coincidence method for a neutron capture detection setup. This consists of two cylindrical deuterated hexabenzene (C6D6) liquid scintillators placed symmetrically and normally with respect to the beam and operated in sum mode. A pulse-height weighting function is derived from this data set and applied to the measurement of neutron capture in the 1.15-keV resonance of 56Fe relative to capture in the 5.2-eV resonance of 109Ag. A value of Γn = 62.9 ± 2.1 meV has been obtained for the neutron width, in good agreement with the value of Γn = 61.7 ± 0.9 meV from transmission measurements. The extension of the validity of this weighting function to samples of different thickness and composition is discussed.
