2017 Fall Meeting
Sep 13 - Sep 15, 2017Hokkaido University
2017 Fall Meeting
Sep 13 - Sep 15, 2017Hokkaido University
[1A05]Reduction and Resource Recycling of High-level Radioactive Wastes through Nuclear Transmutation (LLFP separation )(1)Extraction Behavior of Simulated Fission Products by Chloride Molten Salts
*Akihiro Uehara1, Koichiro Takao2, Yuji Shibahara1(1. Kyoto University Research Reactor Institute, 2. Laboratory for Advanced Nuclear Energy, Institute of Innovative Research, Tokyo Institute of Technology)
Keywords:
vitrified wastes,extraction,molten salt
アルカリ及びアルカリ土類塩化物溶融塩と模擬FPを含むガラスを高温にて接触させ、模擬FPのガラス相からの溶出挙動を調べた。アルカリカチオンあるいはアルカリ土類カチオンの種類に依存して模擬FPの溶出量が異なった。