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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.
Hussein Khalil
Nuclear Science and Engineering | Volume 90 | Number 3 | July 1985 | Pages 263-280
Technical Paper | doi.org/10.13182/NSE85-A17768
Articles are hosted by Taylor and Francis Online.
A diffusion theory method is developed for synthetic acceleration of nodal Sn calculations in multidimensional Cartesian geometries. The diffusion model is derived from the spatially continuous diffusion equation by applying spatial approximations that are P1 expansions of the corresponding approximations made in solving the transport equation. The equations of the diffusion model are formulated in a way that permits application of existing and highly efficient nodal diffusion theory techniques to their numerical solution. Test calculations for several benchmark problems in X-Y geometry are presented to illustrate the efficiency and stability of the acceleration method when applied to a “constant-linear” nodal transport approximation. The method is shown to yield point-wise flux convergence of 10-4 in fewer than ten synthetic iterations for all problems considered and to require substantially less computational effort than unaccelerated solutions.