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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.
Marvin L. Adams, William R. Martin
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 177-189
Technical Paper | doi.org/10.13182/NSE100-177
Articles are hosted by Taylor and Francis Online.
A new class of synthetic acceleration methods, which can be applied to transport calculations regardless of geometry, discretization scheme, or mesh shape, is presented. Unlike other synthetic acceleration methods that base their acceleration on P1 equations, these methods use acceleration equations obtained by projecting the transport solution onto a coarse angular mesh only on cell boundaries. It is demonstrated, via Fourier analysis of a simple model problem as well as numerical calculations of various problems, that the simplest of these methods are unconditionally stable with spectral radius ≤c/3 (c being the scattering ratio), for several different discretization schemes in slab geometry.