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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.
Eishi Ibe, Shunsuke Uchida
Nuclear Science and Engineering | Volume 89 | Number 4 | April 1985 | Pages 330-350
Technical Paper | doi.org/10.13182/NSE85-A18625
Articles are hosted by Taylor and Francis Online.
Dependencies of radiolytic aspects on geometric and operational conditions of boiling water reactor (BWR) primary systems were studied for normal operation or for hydrogen alternate water chemistry (HAWC) by using a computer simulation code AQUARY. Statistical regression analyses were applied to those calculated results and a great many close correlations were found among radiolytic concentrations. In the course of the study, it was discovered that residence time and energy deposition rate in the downcomer had a critical effect on HAWC. A set of simple estimation formulas for radiolytic conditions was proposed for normal BWR operation, and the following prediction formulas were proposed for the oxygen gas release rate and oxygen concentration in the recirculation line under HAWC: .