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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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Latest News
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.
Harold T. Maguire, Jr., Carlos R. S. Stopa, Robert C. Block, Donald R. Harris, Rudolf E. Slovacek, John W. T. Dabbs, Rodney J. Dougan, Richard W. Hoff, Ronald W. Lougheed
Nuclear Science and Engineering | Volume 89 | Number 4 | April 1985 | Pages 293-304
Technical Paper | doi.org/10.13182/NSE85-A18621
Articles are hosted by Taylor and Francis Online.
The fission cross sections of 244Cm, 246Cm, and 248Cm have been measured from 0.1 eV to 80 keV using the Rensselaer Intense Neutron Spectrometer. The cross sections were normalized to the 235U ENDF/B-V broad-bin-averaged fission cross section. Fission areas and widths were determined for the resolved low-energy resonances. In general, the ENDF/B-V fission cross sections for the curium isotopes are in poor agreement with the measured cross sections and a new evaluation of these curium cross sections is recommended. The observation of structure in the measured cross sections in the unresolved region is suggestive of intermediate structure in the even curium isotopes.
