Presentation Information
[1B12]Basic Research Programs of Vitrification Technology for Waste Volume Reduction(136)Research Report of Development of Glass Matrix
*Kohei Owaku1, Katsuhiko HATAKEYAMA1, Takehiro Sumita2, Noritaka Saito2, Toru Sugawara3, Tetsuji Yano4 (1. JNFL, 2. Kyushu Univ., 3. Akita Univ., 4. Science Tokyo)
Keywords:
Nuclear fuel cycle,Radioactive waste,Vitrification,High burnup spent fuel,MOX spent fuel
As part of a project commissioned by the Agency for Natural Resources and Energy of the Ministry of Economy, Trade and Industry "Basic Research Project on Vitrification Technology for Volume Reduction of Radioactive Waste" Japan Nuclear Fuel has carried out "upgrading of glass matrix and supply systems." In this presentation, the outline of the development results of glass matrix for stable treatment of high-level radioactive liquid waste generated during reprocessing of high burnup and MOX spent fuel is reported.
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