Research and Validation on Two-Dimensional Transport-Depletion Program

To describe depletion problems in reactor precisely, the system based on two-dimensional discrete ordinates transport theory and BATEMAN burnup method was set up, and the corresponding code was developed. The matching 175-group neutron and 42-group photon cross section data MUSE-F1.0 was developed based on ENDF/B-Ⅶ. The code was validated with benchmark on MOX fuel fast reactor of OECD/NEA. The computed data are in accord with benchmark, and the error is less than 8%. The results prove that the couple system is feasible in fast reactor transmutation application.