[2O10-13] Vitrification 4

[2O11] Combinatorial approach to investigate the composition of borosilicate glasses with high-loading capacity of high-level nuclear radioactive wastes

*Tetsuji Yano¹, Takuhiro Miyawaki¹, Shinya Ohashi¹, Masahiro Hayashi¹, Tetsuo Kishi¹, Nobuhiro Matsushita¹, Yoshiyuki Miura², Norio Kanehira² (1. Tokyo Institute of Technology, 2. Japan Nuclear Fuel Limited)

Keywords:High-level nuclear radioactive wastes, waste glasses, Yellow phase, Combinatorial method, borosilicate glasses

Improvement of the loading capacity of high-level nuclear radioactive wastes into glass is desired to reduce the number of waste glasses in canister, and finally the space for geological disposal. The loading capacity of nuclear waste is strongly dependent on the composition of glass, and at the same time the glass with high loading capacity has to satisfy the conditions of various kind of properties. Althogh the nuclear wastes are consisted from many kinds of elements and compounds, the molybdenum oxide-containing compounds are quite important constituents to evaluate the loading capacity of glass because they are well known to be contained in glass melt as undissolved phase. In this study, new-type combinatorial approach has been develped to investigate the compositions of borosilicate glass system with high loading capacity of nuclear wastes. Pseudo-wastes were introdued into glass using this technique, and the obtaiend glass samples were evaluated from the precipitation phenomena of molybdenum oxide-containing compounds.