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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.
J. W. T. Dabbs, C. E. Bemis, Jr., S. Raman, R. J. Dougan, R. W. Hoff
Nuclear Science and Engineering | Volume 84 | Number 1 | May 1983 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE83-A17453
Articles are hosted by Taylor and Francis Online.
The fission cross section of 242mAm has been measured from 0.005 eV to 20 MeV using time-of-flight techniques at the Oak Ridge Electron Linear Accelerator. A hemispherical plate fission ionization chamber with five pairs of plates contained three deposits totaling 507 μg of 242mAm, one deposit of 168 μg 235U, and a “weightless” deposit of 252Cf, which served as a monitor of chamber performance. The fission of 235U, served as the cross-section standard for energies above 101 keV while 6Li(n,α), normalized to 235U fission in the 7.8- to 11.0-eV interval, served as a shape standard below 101 keV. Approximately 360 h of data were obtained at a flight path distance of 9.1 m, primarily with 40-ns bursts. Particular attention was paid to correction of backgrounds, especially inscattered-neutron-induced events. The fission resonance integral was found to be 1800 ± 65 b.