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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.
Robert C. Block, Donald R. Harris, Si Hwan Kim, Katsuhei Kobayashi
Nuclear Science and Engineering | Volume 80 | Number 2 | February 1982 | Pages 263-281
Technical Paper | doi.org/10.13182/NSE82-A21430
Articles are hosted by Taylor and Francis Online.
Neutron self-indication measurements simulating 238U capture in reactors have been carried out over the energy range from 3 eV to 3 keV using shielding samples at 77, 293, and 873 K. The data have been reduced to open and self-shielded capture yields provided on magnetic tape as benchmark data for comparison with nuclear design calculations. The important energy range below 100 eV has been analyzed in detail both to obtain improved resonance parameters for the levels at 6.67, 20.9, 36.8, 66.1, and 80.7 eV and to examine the accuracy with which cross sections are calculated from resonance formalisms. The improved resonance parameters, when used with an accurate but practical multilevel formalism, reduce by about one-half the long-standing discrepancy between calculated and measured 238U resonance capture integrals.