Accuracy of Transport Theory Calculations of an Anisotropic Neutron Flux

In this accuracy study, we have solved with the discrete S₂, S₄, and S₈ approximations a monoenergetic half-space problem with a delta-function pencil of neutrons as a source and compared the values of four suitable integral quantities with the results of Monte Carlo calculations. The errors in the space-dependent integrated neutron flux are shown in several figures. Also, tests with different mesh resolutions of the iteration net and with different standard quadrature sets have been made.