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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.
F. U. Ahmed, M. A. Rahman, S. R. Husain, M. M. Rahman
Nuclear Science and Engineering | Volume 85 | Number 4 | December 1983 | Pages 427-430
Technical Note | doi.org/10.13182/NSE83-A18390
Articles are hosted by Taylor and Francis Online.
The dose buildup factors (up to 20 mfp) for gamma rays from a point isotropic 60Co source penetrating multilayered concrete slabs using Cox's Bazar and Sylhet sands have been measured. The instantaneous relaxation lengths (up to 20 mfp) have also been measured for both types of concrete slabs. Some physical properties of concrete blocks of magnetite, Sylhet sand, and a mixture of both types of sand have been measured. Results obtained show that the buildup factors for Sylhet sand slabs increase more rapidly than those of magnetite slabs. The buildup factors for Sylhet sand concrete (ordinary concrete) have been compared with the results obtained from the Berger formula at an energy of 1.25 MeV. The transmission is higher through slabs of Sylhet sand than those of magnetite. Comparing all properties among magnetite slabs, Sylhet sand slabs, and a mixture of magnetite and Sylhet sand slabs, it is found that slabs of a mixture of both sands are more effective for reactor shielding than those comprised of only one of the components.