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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.
Huiquan Qi, Hongbin Chen, Yingtang Chen, Qiankun Chen, Zhenpeng Chen, Zemin Chen
Nuclear Science and Engineering | Volume 111 | Number 3 | July 1992 | Pages 309-313
Technical Paper | doi.org/10.13182/NSE92-A23943
Articles are hosted by Taylor and Francis Online.
A position-sensitive neutron detector is used to measure the differential cross sections of 14.8-MeV neutrons from iron, nickel, and chromium scattered in the angular range of 2.5 to 16 deg. The data are corrected for flux attenuation, multiple neutron scattering, and finite geometry by the Monte Carlo method. The angular distributions are calculated with the coupled-channel code ECIS79. The measured and calculated results are compared and discussed.
