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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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.
E. Dekempeneer, H. Liskien, L. Mewissen, F. Poortmans
Nuclear Science and Engineering | Volume 97 | Number 4 | December 1987 | Pages 353-361
Technical Paper | doi.org/10.13182/NSE87-A23518
Articles are hosted by Taylor and Francis Online.
Double-differential neutron-emission cross sections for the 7Li(n,xn) reaction are presented for average emission angles of 24, 40, 60, 90, 120, and 150 deg. The incident neutron energy covers the range from 1.6 to 13.8 MeV. The cross sections were measured using an electron linear accelerator as a pulsed white neutron source. Elastically scattered neutrons and neutrons scattered via the 0.48-MeV state are treated as one single group. Inelastic scattering cross sections are obtained for the 4.63- and 6.54-MeV states. For this purpose, the underlying neutron continuum coming from competing tritium-producing reactions (three-particle breakup and sequential two-step reaction via the 5He ground state) is estimated using simple physical model calculations. The data are compared with recent evaluations.