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September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Spent fuel transfer project completed at INL
Work crews at Idaho National Laboratory have transferred 40 spent nuclear fuel canisters into long-term storage vaults, the Department of Energy’s Office of Environmental Management has reported.
Shi-tien Yang, A. F. Henry
Nuclear Science and Engineering | Volume 59 | Number 1 | January 1976 | Pages 63-67
Technical Note | doi.org/10.13182/NSE76-A26813
Articles are hosted by Taylor and Francis Online.
A method for obtaining an approximate solution of the group-diffusion equations for geometrically complex reactors is described and tested for a two-group two-dimensional situation. The basic idea of the scheme is to represent the group fluxes throughout a given subassembly as the product of a precomputed normalized “shape function” that accounts for local geometrical detail and a smooth finite element function that specifies the overall magnitude of the fluxes within the subassembly and the gross leakage effects between a given subassembly and its neighbors. These composite fluxes for each subassembly are then stitched together by the application of a variational principle.