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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.
Yunshan Mu, Haishan Xu, Zhengyu Xiang, Yexiang Li, Shiming Wang, Jianfeng Liu
Nuclear Science and Engineering | Volume 108 | Number 3 | July 1991 | Pages 302-307
Technical Note | doi.org/10.13182/NSE91-A23827
Articles are hosted by Taylor and Francis Online.
The radiative capture cross sections of natural niobium and molybdenum are measured relative to that of gold at four neutron energies between 0.7 and 1.4 MeV, using a large liquid scintillation detector and the time-of-flight technique. The neutron capture cross sections from 0.5 to 2.0 MeV for 93Nb and from 0.01 to 2.0 MeV for natural molybdenum are calculated using the optical model and statistical theory. The results are compared with other experimental and calculated data.
