A New Procedure for the Determination of Neutron Multigroup Transfer Matrices

A new technique has been employed to generate Legendre components of group-to-group neutron scattering cross-section matrices for two-body interactions. This semianalytic procedure, which treats the rapidly fluctuating cross-section behavior analytically, has been incorporated in the MINX processor, a code for the Multigroup Interpretation of Nuclear X-sections. The algorithm requires only a minimum of numerical approximations and uses recursive formulas well suited to performing the required integrations. A flexible energy integration mesh is employed so that localized resonance phenomena may be adequately represented.