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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.
C. W. Alexander, J. Halperin, J. B. Knauer, R. L. Walker
Nuclear Science and Engineering | Volume 95 | Number 3 | March 1987 | Pages 194-199
Technical Paper | doi.org/10.13182/NSE87-A20448
Articles are hosted by Taylor and Francis Online.
Two-group integral neutron capture cross sections have been measured for 144Sm and 145Sm. Mass spectrographic assays were carried out on highly enriched samples of 144Sm that were irradiated in a high-flux nuclear reactor making use of cadmium filters and cobalt as a flux monitor. Under the assumption that these nuclides have a (1/ν) dependence in the thermal region, the following are reported: for 144Sm, σc2200 = 1.64 ± 0.10 and Ic = 2.38 ± 0.17 b; for 145Sm, σc2200 = 280 ± 21 and Ic = 600 ± 90 b.