Combining MC2-2 and SCALE cross section methods to process nuclear data for GNEP

This paper describes a joint project by Oak Ridge National Laboratory and Argonne National Laboratory to merge components of the SCALE nuclear analysis system with the MC2-2 code to obtain a more general tool for producing problem-dependent MG cross sections for GNEP and other advanced reactor applications. The complementary aspects of the two methods are described, and the procedure used to couple the codes is outlined. The combined system was used to compute problem-specific self-shielded cross sections for a model of the Advanced Burner Reactor. (authors)