2018 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 405-1 Radioactive Waste Management

[2O19-22] Nuclide Separation and Recovery 2

Tue. Mar 27, 2018 5:00 PM - 6:00 PM Room O (M3-212 -M3 Building)

Chair: Tetsuo Fukasawa (HGNE)

5:00 PM - 5:15 PM

[2O19] Separation and Recovery of LLFPs from Borosilicate Glass

(1)Extraction of Long-Lived Fission Products from Borosilicate Glass with pseudo High-level Radioactive Nuclear Wastes using Ion-Exchange Extraction Method

*Riku Shinjo1, Tetsuji Yano1, Tetsuo Kishi1, Nobuhiro Matsushita1 (1. TIT)

Keywords:ion exchange, High-level nuclear radioactive wastes glasses, Long-Lived-Fission-Products, Borosilicate glass

High-level nuclear radioactive wastes from the reprocessing treatment on the spent fuel are encapsulated in glass, in which Long-Lived Fission Products (LLFP) with half lifetime more than millions of years are contained. In order to treat these waste glasses for geological disposal appropriately, we have to dissolve the issues on the preparation of disposal space. Nuclear transmutation technology enables to shorten the half lifetime of LLFP elements remarkably, and reduces the effort to control waste glasses for long period of time. For this achievement, it is also necessary to extract LLFP elements safely from waste glasses. In this research, we have given our focus on the properties of the heated waste glasses, and developed a new technology to extract LLFP from waste glasses called "Ion-Exchange Extraction method". In this presentation, the results of feasibility test of this technique on the pseudo-waste glasses are shown.