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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Latest News
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.
Gert Van den Eynde, Robert Beauwens, Ernest Mund
Nuclear Science and Engineering | Volume 155 | Number 2 | February 2007 | Pages 300-309
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2664
Articles are hosted by Taylor and Francis Online.
The boundary source method is an integral method introduced in the late 1960s for solving one-dimensional one-velocity transport problems arising in cell calculations. This method was further developed in various ways since that period and found to be of particular interest for recent applications to nodal transport codes. We have developed a boundary source code in plane geometry that allows for anisotropic scattering of arbitrary high order, and it is the purpose of this paper to display the extreme accuracy of this code, showing hereby that the boundary source method is probably the most accurate transport solution method available today for solving piecewise homogeneous transport problems.