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A Numerical Method for Solving Integral Equations of Neutron Transport—II

Sudarshan K. Loyalka, Robert W. Tsai

Nuclear Science and Engineering / Volume 58 / Number 2 / October 1975 / Pages 193-202

Technical Paper / dx.doi.org/10.13182/NSE75-A28222

In a recent paper it was pointed out that the weakly singular integral equations of neutron transport can be quite conveniently solved by a method based on subtraction of singularity. This previous paper was devoted entirely to the consideration of simple one-dimensional isotropic-scattering and one-group problems. The present paper constitutes interesting extensions of the previous work in that in addition to a typical two-group anisotropic-scattering albedo problem in the slab geometry, the method is also applied to an isotropic-scattering problem in the x-y geometry. These results are compared with discrete SN (ANISN or TWOTRAN-II) results, and for the problems considered here, the proposed method is found to be quite effective. Thus, the method appears to hold considerable potential for future applications.