SUMMARY

This thesis will develop and implement a multi-group cross section generation method based on the Monte Carlo method of solving radiation transport problems. The method will be capable of spatially averaging (i.e. homogenizing) and collapsing in energy cross sections in fine-group or continuous energy format. In addition to treating the absorption and fission cross sections, the method will be able to calculate the group-to-group scattering matrix and an arbitrary number of Legendre moments of the angular scattering cross section. For diffusion applications, the capability of calculating stochastic diffusion coefficient will be investigated. The motivation of this thesis is accurately generating collapsed cross sections via a method that is robust with respect to geometry and energy spectrum. The Monte Carlo method is a natural candidate for this task since it produces very accurate results is capable of utilizing either continuous energy or multi-group cross sections and can model a myriad of geometries. This method can be used to generate macroscopic material cross sections for diffusion calculations or transport calculations.