Exact solution of the neutron transport equation for a slab reactor in presence of backward and forward scattering

The effects of a strongly anisotropic scattering law on the critical slab problem in monoenergetic neutron transport theory are studied in this paper using a synthetic kernel. The Boltzmann equation is converted into a single integral equation, which is solved rigorously by a simple and fast convergent projection procedure. Numerical results for critical parameter and critical flux are presented and compared to those already obtained by Siewert and Williams via different semi-analytical algorithms.