Transport-burnup code systems and their applications for IAEA ADS benchmark

Recently for transmutation of spent nuclear fuel, the Accelerator Driven System (ADS) is introduced. Because of anisotropic flux distribution caused by the external source, the nuclear calculation of ADS is significantly different from the traditional nuclear reactor. Two sets of transport burnup code systems based on the transport theory: Monte Carlo-burnup code system and transport-burnup code system are developed, and are applied to IAEA ADS benchmark. Initial enrichments of 233U that correspond to given initial Keff values are calculated. And then, the spatial distributions of power density at BOL, the void reactivity effects, the external source effectiveness, and the evolution curves of Keff and external source as a function of time are also calculated for every given Keff (BOL). The numerical results are in a good agreement with those of participants.