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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.
H-H. Knitter, C. Budtz-Jørgensen
Nuclear Science and Engineering | Volume 99 | Number 1 | May 1988 | Pages 1-12
Technical Paper | doi.org/10.13182/NSE88-A23540
Articles are hosted by Taylor and Francis Online.
The fission cross section of 243Am was measured in the neutron energy range from 1 eV to 10 MeV. Several methods of neutron production were employed using the Van de Graaff accelerator and the electron linear accelerator of the Central Bureau of Nuclear Measurements. The energy averaged fission cross section measured at the Geel electron linear accelerator (GELINA) above 100 eV and the fission cross sections measured at the Van de Graaff above 350 keV were determined relative to the 235U(n,f) cross section. The detailed neutron cross sections measured at GELINA in the 1-eV to 30-keV range were measured relative to the 6Li(n, t)4He cross-section shape and were normalized to the known fission integral of 235U between 7.8 and 11 eV. The present data provide unique new information between 1 and 50 eV. In this energy range, fission areas from 31 resonances were determined. In the subthreshold region above 100 eV, the present results demand drastic corrections of the evaluated data files by factors up to 6. Between the first and second chance fission threshold, the present experiment supports the ZEBRA integral experiment, which suggested a reduction of the fission cross section of 243Am in this region by 12% with respect to an earlier data set.