During the operation of nuclear power plant (NPP), the concentrates and spent resin are generated. They show relatively high radioactivity compared to other radioactive waste, such as dry active waste, charcoals, and concrete wastes. The waste acceptance criteria (WAC) of disposal facility defines the structure and property of treated waste. The concentrates and spent resin should be solidified or packaged in high integrity container (HIC) to satisfy the WAC in Korea. The Kori NPP has stored history waste. The large concrete package with solidified concentrates and spent resin. The WAC requires identification of 18 properties for the radioactive waste. Since some of the properties are not clearly identified, the large concrete packages could not satisfy the WAC in this moment. The generation of the large concrete package (rectangular type and cylindrical type), pretreatment of the package, treatment of inner drum, process development for clearance waste, etc. will be discussed in this paper. In addition, the conceptual design of whole treatment process will be discussed.

• Young Hwan Hwang(Korea Hydro and Nuclear Power (KHNP) Central Research Institute (KHNP-CRI)) Corresponding author
• Mi-Hyun Lee(Korea Hydro and Nuclear Power (KHNP) Central Research Institute (KHNP-CRI))
• Seok-Ju Hwang(Korea Hydro and Nuclear Power (KHNP) Central Research Institute (KHNP-CRI))
• Jung-Kwon Son(Korea Hydro and Nuclear Power (KHNP) Central Research Institute (KHNP-CRI))
• Cheon-Woo Kim(Korea Hydro and Nuclear Power (KHNP) Central Research Institute (KHNP-CRI))
• Chang-Kyu Kim(Doosan Enerbility)