الفهرس 
Introduction
Practical formulationOnly 14 pages are availabe for public view
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Abstract
The green’s function formalism developed by Case [59] to solve the boundary value problem of neutron transport is used to include the surface source contribution to the discrete integral transport method developed by Carlvik [13] and to generalized the collision probability method. Two equations are obtained for the expansions coefficients of the flux in spherical harmonics. The transport kernels appeared in these equations can be expressed in terms of Bickely functions.