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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.
W. Hage, D. M. Cifarelli
Nuclear Science and Engineering | Volume 89 | Number 2 | February 1985 | Pages 159-176
Technical Paper | doi.org/10.13182/NSE85-8
Articles are hosted by Taylor and Francis Online.
A mathematical model is derived for the probability distribution of neutron signal multiples inside randomly and signal triggered time intervals for a generalized time response function of the neutron detector assembly. The theory is applied to assemblies with an exponential time decay of its neutron population. The probability distributions, their factorial moments, and moments are expressed as a function of the spontaneous fission rate, (α-n) reaction rate, neutron detection probability, probability that a neutron generates a fast fission, and nuclear data. Measurements with a plutonium sample are analyzed to check the derived algorithms for the factorial moments of the two probability distributions.