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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.
R. Gwin, R. R. Spencer, R. W. Ingle, J. H. Todd, S. W. Scoles
Nuclear Science and Engineering | Volume 88 | Number 1 | September 1984 | Pages 37-55
Technical Paper | doi.org/10.13182/NSE84-A17138
Articles are hosted by Taylor and Francis Online.
Measurements were made of the energy dependence of the 235U neutron fission cross section over the energy range from 0.01 eV to 30 keV and of the 239Pu fission cross section over the range from 0.01 to 60 eV. The energy integral of the fission cross section for 235U was normalized to 19.26 b·eV in the 0.0206- to 0.06239-eV interval; this yielded a value of 248 ± 1.7 b·eV for the 7.8- to 11-eV interval, which is in good agreement with other measurements normalized in the same manner. The energy integral for 239Pu was normalized to 25.15 b·eV in the 0.02001- to 0.06001-eV interval; the resulting value of 504 b·eV in the 9- to 12.6-eV interval was also in good agreement with other data. For the energy ranges covered, the energy dependence of both the 235U fission cross section and the 239Pu fission cross section is consistent with ENDF/B-V data except f or a few energy intervals in which the 235U cross section differs by as much as 4%.