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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.
K. Böhnel
Nuclear Science and Engineering | Volume 90 | Number 1 | May 1985 | Pages 75-82
Technical Paper | doi.org/10.13182/NSE85-2
Articles are hosted by Taylor and Francis Online.
Time correlation analysis of neutron detection is routinely applied in the quantitative determination of spontaneously fissioning isotopes, especially plutonium. Since these materials are usually also fissionable by the neutrons emitted, multiplication must be taken into account. A method is presented that allows calculation of the effect on characteristic parameters of the assay. These are the factorial moments of the probability distribution of the multiplicities of the neutrons emitted. The results can be written as analytic functions of the fission probability. They are given for the case of an energy spectrum common to all types of neutrons and for cases in which the source spectrum influences the probability of fission or the efficiency of detection.