2023 Fall Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 505-1  Radioactive Waste Management

[1E15-19] Vitrification 3

Wed. Sep 6, 2023 4:45 PM - 6:00 PM Room E (Okuma Machine Tool Eng. Bildg. 1F Okuma Hall)

Chair:Satoshi Okada(HGNE)

4:45 PM - 5:00 PM

[1E15] Basic Research Programs of Vitrification Technology for Waste Volume Reduction

(121) Evaluation of the behavior of γ-ray degraded products generated from adsorbent for Extraction Chromatography

*Yu Kazama1, Hiroki Fukumoto1, Yasunori Miyazaki2, Yuichi Sano2 (1. Ibaraki Univ., 2. JAEA)

Keywords:Extraction chromatography, TEHDGA adsorbent, γ-ray decomposition

Radioactive liquid waste generated from spent fuel reprocessing will be disposed of in a geological formation after vitrification, and will be stored and managed for tens of thousands of years. From the viewpoint of reducing the thermal load in the repository, it has been shown that separation of minor actinides (MA; Am, Cm) contained in radioactive liquid waste is effective in reducing the number of vitrified products. In this study, we focused on the radiolysis of TEHDGA adsorbent for extraction chromatography. The presumed degraded products were synthesized and quantified by GC/MS analysis to clarify the formation behavior of the degraded products by γ-ray irradiation.

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