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Optimization of Chemical Composition in the Iron Phosphate Glass as the Matrix of High Level Waste Generated From Pyroprocessing

[+] Author Affiliations
Hirohide Kofuji

Japan Atomic Energy Agency, Tokai, Ibaraki, Japan

Tetsuji Yano

Tokyo Institute of Technology, Tokyo, Japan

Munetaka Myochin

Japan Atomic Energy Agency, Tsuruga, Fukui, Japan

Kanae Matsuyama, Takeshi Okita, Shinya Miyamoto

Toshiba Corporation, Kawasaki, Kanagawa, Japan

Paper No. ICONE22-30688, pp. V004T08A010; 6 pages
doi:10.1115/ICONE22-30688
From:
  • 2014 22nd International Conference on Nuclear Engineering
  • Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory
  • Prague, Czech Republic, July 7–11, 2014
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-4594-3
  • Copyright © 2014 by ASME

abstract

As part of ongoing research and development of nuclear waste disposal techniques suitable for the pyrochemical processing system [1], iron-phosphate glass was examined as an alternative waste form for high level waste generated from the electro-refining process [2]. To enhance the waste element content in the glass matrix and improve the durability of the waste form, optimization experiments of the glass composition were performed, and the effects of other additional transition metal oxides were determined. From the surface analysis of iron phosphate glass, a leaching mechanism was assumed for various elements contained in the glass matrix. We have selected suitable a glass composition for the treatment of radioactive waste generated from the spent electrolytes of pyrochemical processing.

Copyright © 2014 by ASME
Topics: Glass , Optimization , Iron

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