In this work, a combination of forward and backward scattering is studied for the numerical solution of one-dimensional neutron transport problems in a finite homogeneous slab and sphere. The scattering of the neutrons is assumed to be anisotropic for the slab and isotropic for the spherical geometry. Numerical solutions are carried out by using both the spectral Green's function (SGF) and the diamond-difference (DD) methods to check the accuracy of the results. Calculated numerical results of cell-edge scalar fluxes are presented in the tables
A spectral analysis of the transport kernel for anisotropic scattering in finite slabs is achieved b...
Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...
We present a method for solving the two-dimensional equation of transfer. The method can be extended...
The spectral Green's function (SGF) method is used to solve numerically the transport of neutrons in...
The UN method is used to solve the critical slab problem for reflecting boundary conditions in one-s...
The eigenvalue spectrum is studied for one-speed neutrons in a slab with forward and backward scatte...
An extension of the Green's function method is developed for the exact solution of the multigroup ne...
The critical slab problem in the case of combination of forward and backward scattering with usual i...
The neutron transport equation for a slab geometry with the extremely anisotropic scattering kernel ...
WOS: 000245230000010The U-N method is used to solve the critical slab problem for reflecting boundar...
WOS: 000245403100004The critical slab problem in the case of combination of forward and backward sca...
The integral form of the one-speed, steady-state Boltzmann transport equation is solved for a point ...
First estimates for the numerical solution of the one-dimensional neutron transport equation for one...
International audienceIn nuclear reactor physics, neutron transport in media having anisotropic prop...
A Green's function technique is applied to one‐velocity neutron problems with spherical symmetry. Th...
A spectral analysis of the transport kernel for anisotropic scattering in finite slabs is achieved b...
Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...
We present a method for solving the two-dimensional equation of transfer. The method can be extended...
The spectral Green's function (SGF) method is used to solve numerically the transport of neutrons in...
The UN method is used to solve the critical slab problem for reflecting boundary conditions in one-s...
The eigenvalue spectrum is studied for one-speed neutrons in a slab with forward and backward scatte...
An extension of the Green's function method is developed for the exact solution of the multigroup ne...
The critical slab problem in the case of combination of forward and backward scattering with usual i...
The neutron transport equation for a slab geometry with the extremely anisotropic scattering kernel ...
WOS: 000245230000010The U-N method is used to solve the critical slab problem for reflecting boundar...
WOS: 000245403100004The critical slab problem in the case of combination of forward and backward sca...
The integral form of the one-speed, steady-state Boltzmann transport equation is solved for a point ...
First estimates for the numerical solution of the one-dimensional neutron transport equation for one...
International audienceIn nuclear reactor physics, neutron transport in media having anisotropic prop...
A Green's function technique is applied to one‐velocity neutron problems with spherical symmetry. Th...
A spectral analysis of the transport kernel for anisotropic scattering in finite slabs is achieved b...
Includes bibliographical references (leaves 265-277)A new numerical method is developed to solve the...
We present a method for solving the two-dimensional equation of transfer. The method can be extended...