[1K06-09] Waste Management 1

[1K09] Development of glass matrices with high loading capacity and feeding forms for melting of high-level nuclear wastes from high-burnup and/or MOX spent fuels

*Tetsuji Yano¹, Mizuto Saito¹, Hiroyuki Kadono¹, Tetsuo Kishi¹, Takeshi Tsukada², Kohei Oowaku², Ryou Souma² (1. Tokyo Institute of Technology, 2. Japan Nuclear Fuel Limited)

Keywords:high-level nuclear wastes, Vitrification, High-burnup spent fuel, MOX spent fuel, glass matrices

New glass matrices and feeding forms are requested to be newly developed for coming high-level nucear wastes from high-burnup and/or MOX spent fuels, which have different chemical compositions from present wastes. This research has been done for the developmemnt of new borosilicate glass matrices and feeding form suitable for the vitrification of these new wastes. This presentation reports the achievments and present status of this work.