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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. F. McFarlane, S. G. Carpenter, P. J. Collins, D. N. Olsen, S. B. Brumbach
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 204-232
Technical Paper | doi.org/10.13182/NSE84-A17779
Articles are hosted by Taylor and Francis Online.
Experimental programs to investigate the physics characteristics of heterogeneous liquid-metal fast breeder reactor cores have been conducted in the zero-power plutonium reactor critical facility over a period of ∼ 5 yr. Previous experiments on conventional homogeneous cores provided appropriate benchmark data against which to judge the heterogeneous core results. For a heterogeneous reactor of the Clinch River Breeder Reactor size, both the physics parameters and the ability to predict them by common design methods differ substantially from an equivalent conventional design. Data errors and methods approximations have a greater effect in the analysis of heterogeneous cores, particularly with respect to such spatially varying parameters as power distributions and control rod worths. Preliminary results from recent experiments on a 700-MW(electric)-sized heterogeneous assembly are presented. As expected, predictions of physics parameters in general are worse than for conventional cores. Eigenvalue spectra and cross-section sensitivity have been used to characterize the spatial sensitivity of the cores.