Spectral Green's function method for neutron transport: isotropic, forward, and backward scattering in 1-D slab geometry
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference8 articles.
1. A spectral nodal method for one-group X,Y,Z-cartesian geometry discrete ordinates problems
2. Treatment of Anisotropic Scattering in Numerical Neutron Transport Theory
3. A Numerical Method for One-Group Slab-Geometry Discrete Ordinates Problems with No Spatial Truncation Error
4. A Spectral Nodal Method for One-GroupX, Y-Geometry Discrete Ordinates Problems
5. Lewis E.E., Miller W.F., 1984. Computational Methods of Neutron Transport, vol. 116. John Wiley & Sons, New York.
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1. S4 solution of the transport equation for eigenvalues using Legendre polynomials;EPJ Web of Conferences;2017
2. Numerical results for the transport equation with strongly anisotropic scattering in a slab;Annals of Nuclear Energy;2015-05
3. Spectral Green's Function Method for Neutron Transport with Backward and Forward Scattering in 1‐D Slab and Spherical Geometry;Transport Theory and Statistical Physics;2006-09
4. An analytic and numerical solution with spectral Green's function method for transport equation in spherical geometry;Journal of Quantitative Spectroscopy and Radiative Transfer;2005-01
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