Few Group Burnup Calculations Using Time Dependent Microscopic Cross Sections

Abstract

The main drawback of using lattice cell codes in the daily calculation of burnup dependent fewgroup homogenized fuel cross sections is the extensive computer effort that it requires. Many options for speeding up this process can be considered including a reduction of the number of energy groups to be treated in the successive transport solution required at the various burnup steps. Here, we suggest a method for generating time dependent fewgroup microscopic cross sections and discuss how they can be used for fuel depletion calculations.