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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.
Albert E. Richardson, Harold L. Wright, John L. Meason, James R. Smith
Nuclear Science and Engineering | Volume 94 | Number 4 | December 1986 | Pages 413-425
Technical Note | doi.org/10.13182/NSE86-A18351
Articles are hosted by Taylor and Francis Online.
The mass-yield distribution of fission products following degraded-fission-spectrum neutron-induced fission of 232Th was measured by gamma spectrometry for 25 mass chains including mass 138 for the first time for fast fission. Cumulative yields for 83gSe and 130gSb were observed, the latter also for the first time for fast fission. In general, the yields for degraded-fission-spectrum neutron-induced fission of 232Th were slightly higher in the inner portions of both the heavy and light mass wings than for those from reactor-neutron-induced fission of 232Th. This was expected, since the average energy of degraded-fission-spectrum neutrons is slightly above that of reactor neutrons.
