Neutron Transport Calculations in Cylindrical Geometry

An integral transformation technique and the F_N method are used to solve, for the case of isotropic scattering, the albedo problem and the internal-source problem relevant to neutron transport theory for a bare cylinder of infinite length. The neutron flux distribution and the neutron current distributions are found with five or six figures of accuracy and are tabulated for selected illustrative cases. In addition, selected results for the albedo are reported with an accuracy of eight to ten significant figures.