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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.
M. M. Meier, W. B. Amian, C. A. Goulding, G. L. Morgan, C. E. Moss
Nuclear Science and Engineering | Volume 110 | Number 3 | March 1992 | Pages 299-301
Technical Note | doi.org/10.13182/NSE92-A23902
Articles are hosted by Taylor and Francis Online.
Absolute neutron yields from stopping-length targets at angles of 7.5, 30, 60, and 150 deg for the 256-MeV proton bombardment of elemental beryllium, carbon, aluminum, and iron are measured. Time-of-flight techniques are used to identify and discriminate against backgrounds and to determine the neutron energy spectrum. Comparison of the experimental data with intranuclear-cascade evaporation-model calculations using the HETC code showed good agreement, indicating that transport probably dominates production effects in the calculations.