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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. T. Jones, J. S. Merritt, A. Okazaki
Nuclear Science and Engineering | Volume 93 | Number 2 | June 1986 | Pages 171-180
Technical Paper | doi.org/10.13182/NSE86-A17666
Articles are hosted by Taylor and Francis Online.
The thermal neutron capture cross section of 232Th has been measured relative to that of 197Au. Foils of gold, thorium metal, and thoria were irradiated together in the NRU reactor thermal column. The 198Au activity was assayed in a 4πγ ionization chamber, which had been previously calibrated with samples of 198Au standardized by the 4π Β-γ coincidence method. Protactinium-233 sources were also standardized by this method. Comparison of these sources with the irradiated thorium, by means of a Ge(Li) spectrometer, enabled the 233Pa activity in the thorium-bearing foils to be determined. Taking the 2200 m/s capture cross section of 197Au to be 98.8 b, that of 232Th is found to be 7.33 ± 0.06 b. The uncertainty is at the 95% confidence level and includes an estimate of the systematic uncertainties.