The spent fuel of current nuclear reactors is one of challenging issues for the continuous utilization of nuclear power. As a technical solution, deep geological disposal and partitioning & transmutation (P&T) technology have been studied for decades. During the study of P&T technology, concept of LLW generation through the P&T by separation of high heat-load and activity FP has been previously proposed. A study on the PEACER transmutation reactor and pyroprocess-based partitioning system in Korea are suggested with the concept of converting all the spent fuel from PWR into LLW disposable to near-surface disposal facility.
In this study, the feasibility of near-surface disposal for waste from PEACER & pyroprocessing is evaluated in the view point of decontamination factor (DF) applied to pyroprocessing and risk-based waste classification system. For the study, waste characteristics and mass balance from PWR and PEACER is predicted. Waste acceptance criteria of disposal facility are derived by considering domestic scenarios and facility. The effect of important parameter, especially, waste isolation period and waste stabilization, is considered.
It is concluded that the feasibility of near-surface disposal for waste from PEACER and pyroprocessing system strongly depends on the decontamination factor and the long-term waste isolation period and more stable waste stabilization than by commercial concrete material are required to reduce acceptable DF value.