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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.
Ricardo C. De Barros, Edward W. Larsen
Nuclear Science and Engineering | Volume 111 | Number 1 | May 1992 | Pages 34-45
Technical Paper | doi.org/10.13182/NSE92-A23921
Articles are hosted by Taylor and Francis Online.
A new nodal method is developed for the solution of one-group discrete ordinates (SN) problems with linearly anisotropic scattering in x,y-geometry. In this method, the “spectral Green’s function” (SGF) scheme, originally developed for solving SN problems in slab geometry with no spatial truncation error, is generalized to solve the one-dimensional transverse-integrated SN nodal equations with the “constant” approximation for the transverse leakage terms. The resulting “SGF-constant nodal” (SGF-CN) method is more accurate than conventional coarse-mesh methods for deep penetration problems because it treats the scattering source terms implicitly and exactly; the only approximation involves the transverse leakage terms. In conventional SN nodal methods, the transverse leakage terms and scattering source are both approximated. We solve the SGF-CN equations using the one-node block inversion iterative scheme, which uses the best available estimates for the node-entering fluxes to evaluate the node-exiting fluxes in the directions that constitute the incoming fluxes for the adjacent nodes as the equations are swept across the system. Finally, we give numerical results that illustrate the accuracy of the SGF-CN method for coarse-mesh calculations.