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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. Santoro, J. M. Barnes, R. G. Alsmiller, Jr., P. D. Soran
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 260-270
Technical Paper | doi.org/10.13182/NSE83-A17794
Articles are hosted by Taylor and Francis Online.
Neutron and gamma-ray energy spectra resulting from the streaming of 14-MeV neutrons through a 0.30-m-diam duct (length-to-diameter ratio = 2.83) have been calculated using the Monte Carlo MCNP code. The calculated spectra are compared with measured data and data calculated previously using a combination of discrete ordinates and Monte Carlo methods. Comparisons are made at 12 detector locations on and off the duct axis for neutrons with energies above 850 keV and for gamma rays with energies above 750 keV. The neutron spectra calculated using MCNP agree with the measured data within ∼5 to ∼50%, depending on detector location and neutron energy. Agreement with the measured gamma-ray spectra is also within ∼5 to ∼50%. The spectra obtained with MCNP are also in favorable agreement with the previously calculated data and were obtained with less calculational effort.