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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.
J. W. Boldeman, B. E. Clancy, D. Culley
Nuclear Science and Engineering | Volume 93 | Number 2 | June 1986 | Pages 181-192
Technical Paper | doi.org/10.13182/NSE86-2
Articles are hosted by Taylor and Francis Online.
The prompt neutron emission spectrum from the spontaneous fission of 252Cf has been measured for the 0.124- to 15.0-MeV energy range. In the measurement program, seven separate measurements were made of the spectrum between 7.0 and 15.0 MeV using a plastic scintillator as the neutron detector. For the 0.124- to 2.66-MeV energy range, a 6Li glass scintillator was used as the neutron detector. The data are presented with respect to a Maxwellian distribution with T = 1.42 MeV. Some positive and negative deviations with respect to this distribution have been observed.
