Monte Carlo-burnup code system and it's application to IAEA ADS benchmark

For transmutation of spent nuclear fuel, the Accelerator Driven System(ADS) is introduced. Because of anisotropic flux distribution caused by external source, the nuclear calculation of ADS is significantly different with the normal nuclear reactor's. It is necessary to apply the transport theory method. Therefore. IAEA issued an ADS benchmark, which was divided into several stages, and The 1st stage devoted to analyzing neutron performances of ADS and validating the nuclear databases and the codes used for ADS computation. A transport and burnup code system MCNT-ORLGEN2 is developed. Initial enrichments of233 U which correspond to given initial (BOD Keff values are calculated. And then, the spatial distributions of power density (BOL) ,the void reactivity effects,the spallation source effectiveness φ* , and the evolution curves of Keff and source as function of time are also calculated for each given Keff(BOL). The numerical results are in a good agreement with those of various countries.