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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.
Masayoshi Sugimoto, Alan B. Smith, Peter T. Guenther
Nuclear Science and Engineering | Volume 97 | Number 3 | November 1987 | Pages 235-238
Technical Note | doi.org/10.13182/NSE87-A23505
Articles are hosted by Taylor and Francis Online.
The prompt fission neutron spectrum resulting from 239Pu fission induced by ∼0.55-MeV incident neutrons is measured from 1.0 to 10.0 MeV relative to that of 235U fission induced by the same incident energy neutrons. The measurements employ the time-of-flight technique. Energy-dependent ratios of the two spectra are deduced from the measured values. The experimentally derived ratio results are compared with those calculated from ENDF/B-V (revision 2) and with results of recent microscopic measurements. Using the ENDF/B-V 235U Watt parameters for the 235U spectrum, the experimental measurements imply a ratio of average fission spectrum energies of 239Pu/235U = 1.045 ± 0.003, compared to the value 1.046 calculated from ENDF/B-V (revision 2).