Feasibility study on vitrification of low-and intermediate-level radioactive waste from pressurized water reactors

摘要

In order to obtain annual generation volume and composition data for low-and intermediate-level radioactive waste (LILW), characteristics and generation trends for each waste which was produced at nuclear power plants (NPPs) in Korea were inveti- gated. The data were utilized in laboratory scale vitrification experiments and in a technical and economic assessment for LILW vitrification. For technical assessment, four promising melters, which were the cold curcible melter heated by direct induction (CCM), the cold crucible melter heated by vertical electrodes (CCVE), the quantum catalytic extraction process (QCEP), and the plasma torch melter (PT), were selected and evaluated to determine the best available melter.