Development of radiation characteristics analysis code system for geological disposal and application to vitrified waste disposal with various LWR burnup conditions

•The radiation characteristics analysis code system for geological disposal is developed to study the radiation influences of high-level waste disposal for various conditions from a reactor burnup through geological disposal.•The effect of the burnup condition in light water reactor on the radiation characteristics in vitrified waste is analyzed by considering the processes from core burnup though final disposal conditions.•The utilization of MOX fuel increases the MA radioactivity drastically, thereby increasing the neutron emission rate of waste and the neutron flux on the canister surface by more than nine times.•The utilization of high burnup fuel increases the radiation emission rate and flux by 20 – 120 % but it is less effective than the utilization of MOX fuel.