Validation analysis of burnup code MVP-ORBURN using the SFCOMPO database

A series of burnup calculations was conducted for typical post irradiation experimental data prepared in SFCOMPO using Jones's MVP-ORBURN code, which is a coupling codes of MVP-II and ORIGEN2. The analyzed cases cover a wide range of data including four pressurized water reactors (PWRs) and three boiling water reactors (BWRs). As long as the post-irradiation composition of major actinides applied in the Level 1 burnup credit are concerned, the calculation results of end of cycle (EOC) compositions obtained using the JENDL-3.3 nuclear data library showed a good agreement within a range of 10% discrepancy between the calculations and the experiments. Consequently, the code system is found to be sufficiently applicable to burnup credit evaluations. (authors)