BACK-AND-FORTH APPROXIMATION AS A SIMPLE NEUTRON TRANSPORT MODEL

摘要

The back-and-forth approximation is a very simple neutron transport model that helps get a number of exact solutions which qualitatively describe the actual characteristics of planar, cylindrical and spherical systems with fissile material. The model allows its absolutely accurate implementation in Monte Carlo codes and can be used to test the algorithms which do not treat geometry or interaction data.