The integral-transform method for solving neutron transport problems with general anisotropic scattering in a cylinder of finite height
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference19 articles.
1. Factorized Kernels and the DKPL Solution to the Third Form of the Neutron Transport Equation in a Rectangular Parallelepiped
2. A reduced three-dimensional transport equation with anisotropic scattering
3. IV. The triplets of helium
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1. Behaviour of criticality eigenvalues of one-speed transport operator with linearly anisotropic scattering;Annals of Nuclear Energy;1997-01
2. Nonmonotonic behavior of the ‘C’ eigenvalue of the one-speed neutron transport problem in two-dimensional cylindrical (R,Z) geometry;Transport Theory and Statistical Physics;1994-06
3. Radiative transfer in media with cylindrical symmetry;Physica Scripta;1991-06-01
4. Criticality and time eigenvalues in one-speed neutron transport;Progress in Nuclear Energy;1990-01
5. The energy-dependent radiation transfer in a homogeneous finite cylinder;Astrophysics and Space Science;1990
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