Activation calculations for components of a pressurized water reactor

In Switzerland the owners of nuclear power plants are responsible for the radioactive waste disposal and the respective financial reserves for decommissioning. Every 5-10 years the radioactive inventory of reactor internals, reactor pressure vessel (RPV) and neutron irradiated structures in the RPV surrounding has to be determined. The authors describe the generic calculations for PWR reactors using the Monte Carlo Code MCNP5 for the neutron transport calculations and the GRSAKLTIV-II code based on ORIGEN for the activation analysis. The neutron cross sections are based on ENDF/B-VI- und JEFF 3.1 data. The activation calculations were performed for Co-60, - in the future calculations for other nuclides are planned. The model will be extended to the primary circuit in order to consider streaming effects.