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Compositional dependence on the local structure of the simulated nuclear waste glass samples

Okamoto, Yoshihiro  ; Masuno, Atsunobu*; Owaku, Kohei*; Tsukada, Takeshi*; Kanehira, Norio*

In the development of vitrification technology for high burnup fuel and MOX fuel, tests using various compositions of raw glass materials were conducted to find the optimum composition. The Si/B ratio and the amount of alkali in the raw glass, and even the loading ratio of waste components were varied. In this study, we summarize the composition dependence obtained by structural analysis of those samples.

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