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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
B. D. Ganapol, J. K. Patel
Nuclear Science and Engineering | Volume 200 | Number 1 | March 2026 | Pages S270-S282
Research Article | doi.org/10.1080/00295639.2024.2445987
Articles are hosted by Taylor and Francis Online.
The linear one-dimensional (1D) monoenergetic transport equation is likely the most studied transport equation in radiative transfer and neutron transport investigations. Nearly every method imaginable has been applied to establish solutions, including Laplace and Fourier transforms, singular eigenfunctions, Weiner-Hopf, PN expansions, double PN expansions, Chebychev expansions, Lagrange polynomial interpolation, numerical discrete ordinates with finite difference, analytical discrete ordinates, finite elements, integral equations, adding and doubling, invariant imbedding, solution of Ricatti equations and response matrix methods—and probably more, of which the authors are unaware. Of those listed, the response matrix solution to the discrete ordinates form of the 1D transport equation is arguably the simplest and most straightforward. Here, we propose another analytical response matrix solution based on exponentials but to the first order equation enabled by matrix scaling.