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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.
K. Thurnay
Nuclear Science and Engineering | Volume 82 | Number 2 | October 1982 | Pages 181-189
Technical Paper | doi.org/10.13182/NSE82-A28700
Articles are hosted by Taylor and Francis Online.
Temperature- and density-dependent functions were constructed for the pressure, heat capacity, and thermal conductivity of sodium. In evaluating these functions, the latest available sodium data were used. The near critical part of the properties was modeled with the method of the critical exponents. Each function is defined for all temperatures above the melting point and for all densities below the density of the liquid.