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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.
Eugene Goldberg, Ronald L. Barber, Patrick E. Barry, Norman A. Bonner, James E. Fontanilla, Clyde M. Griffith, Robert C. Haighf David R. Nethaway, George B. Hudson
Nuclear Science and Engineering | Volume 91 | Number 2 | October 1985 | Pages 173-186
Technical Paper | doi.org/10.13182/NSE85-A27440
Articles are hosted by Taylor and Francis Online.
Tritium production cross sections have been inferred from direct measurements of tritium generated in wafers of 6LiH and 7LiH under bombardment by 15-MeV neutrons produced at the Lawrence Livermore National Laboratory's Rotating Target Neutron Source-I facility. Sealed in a thin-walled lead container, each hydride wafer was immersed in boiling mercury that first amalgamated the lead and then dissociated the LiH. The hydrogen, acting as a carrier, was directed to an electronic counter and mixed carefully with methane. The counting procedure provided an accurate measure of tritium originally generated in each wafer. The TART Monte Carlo code was employed in the analysis of the data. The tritium production cross section for 6Li exposed to 14.92-MeV neutrons is 32 ±3 mb and that for 7Li exposed to 14.94-MeV neutrons is 302 ± 18 mb.