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May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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. C. No, M. S. Kazimi
Nuclear Science and Engineering | Volume 81 | Number 3 | July 1982 | Pages 319-324
Technical Paper | doi.org/10.13182/NSE82-A20277
Articles are hosted by Taylor and Francis Online.
The wall heat transfer coefficient for the forced convective two-phase flow of sodium is theoretically derived by using the momentum-heat transfer analogy and a logarithmic law for the velocity distribution in the liquid film. Only one constant in this logarithmic form needs to be empirically determined. The relationship between the film average temperature and the interfacial liquid-vapor temperature is also derived. The results from the suggested correlation are in excellent agreement with the Zeigarnick and Litvinov data over a broad range of parameters. The predictions are also in agreement with the high heat transfer coefficient observed in some General Electric Company experiments. The proposed correlation is found to result in a higher heat transfer coefficient for sodium than do the previously advanced correlations.