Preliminary Study on Risk Identification and Assessment Framework for Fusion Radioactive Waste Management

Figure 1

BHPs of fusion in-vessel components, including component replacement. This fusion reactor has an installed capacity of 1 GWe and PbLi breeding blankets design [10]. The irradiation duration for blankets and divertors are 5 years and 2.5 years, respectively. The duty time of the VV is the entire plant life. The radionuclide inventory after 30 years of operation is calculated by neutronics code SuperMC [19] and FENDL3.1 data library [20], and BHP is obtained by dividing the inventory for each nuclide by its maximum permissible concentration in water. The tritium contribution to BHP has been removed, considering the detritiation process in the fusion radwaste treatment. For the PWR, the weight of spent fuel is approximately 30 tons and refueling is carried out every 1.5 years.