
doi: 10.2172/662029
The purpose of this study was to identify and provide an evaluation of interim storage facilities and potential facility locations for the vitrified high-level waste (HLW) from the Phase I demonstration plant and Phase II production plant. In addition, interim storage facilities for solidified separated radionuclides (Cesium and Technetium) generated during pretreatment of Phase I Low-Level Waste Vitrification Plant feed was evaluated.
05 Nuclear Fuels, High-Level Radioactive Wastes, Radioactive Waste Storage, Technetium, Cesium, Low-Level Radioactive Wastes, Vitrification
05 Nuclear Fuels, High-Level Radioactive Wastes, Radioactive Waste Storage, Technetium, Cesium, Low-Level Radioactive Wastes, Vitrification
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