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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.
P. L. Reeder, R. A. Warner
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 181-189
Technical Note | doi.org/10.13182/NSE84-A17710
Articles are hosted by Taylor and Francis Online.
Evaluated delayed neutron emission probabilities for 74 precursors and estimated probabilities for another 174 precursors have been combined with ENDF/B-V fission yields to map out delayed neutron yields as a function of mass number, proton number, and neutron number. For all fissioning systems, more than 90% of the delayed neutron yield comes from precursors with measured Pn values. Most of the remaining yield comes from the precursors 88As, 100–103Y, and 137Sb. High priority should be given to Pn measurements for these precursors. Periodic peaks about five mass numbers apart are seen when delayed neutron yields are plotted versus mass number. This behavior is explained by the very strong enhancement of yields from odd Z precursors. Even Z precursors contribute <10% of the total delayed neutron yield. Plots of delayed neutron yields versus neutron number show dramatic decreases at the closed shell numbers 50 and 82 and smaller effects at subshell numbers 40 and 56. A procedure based on calculated and total delayed neutron yields is proposed for determining proton pairing factors in the fission yield model.