This study is carried out to make the pyroprocessing hold a competitive advantage from the viewpoint of environmental load reduction and economical improvement. As one of the measures to reduce the volume of the high-level radioactive waste (HLW), the phosphate conversion method is applied for removal of fission products (FP) from the melt, referring to the spent electrolyte in this paper. Among the removing target chlorides in the spent electrolyte i.e., alkali metals, alkaline earth metals and rare earth elements, only the rare earth elements and lithium form the precipitates as insoluble phosphates by reaction with Li3PO4. The sand filtration method was applied to separate FP precipitates from the spent electrolyte. The iron phosphate glass (IPG) powder, which is a compatible material for the immobilization of FP, was used as a filter medium. After filtration experiment, it was proven that insoluble FP could almost be completely removed from the spent electrolyte. Subsequently, we attempted to separate the dissolved FP from the spent electrolyte. The IPG was being used once again but this time as a sorbent instead. This is possible because the IPG has some unique characteristics, e.g., changing the valence of iron, which is one of its network modifiers due to its manufacturing temperature. Therefore, it would be likely to sorb some FP when the chemical condition of IPG is unstable. We produced three kinds of IPG under different manufacturing temperature and confirmed that those glasses could sorb FP as anticipated. According to the experimental result, its sorption efficiency of metal cations was attained at around 20–40%.
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ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management
October 3–7, 2010
Tsukuba, Japan
Conference Sponsors:
- Nuclear Engineering Division and Environmental Engineering Division
ISBN:
978-0-7918-5453-2
PROCEEDINGS PAPER
Removal of Fission Products in the Spent Electrolyte Using Iron Phosphate Glass as a Sorbent
Ippei Amamoto,
Ippei Amamoto
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Naoki Mitamura,
Naoki Mitamura
Central Glass Co., Ltd., Matsuzaka, Mie, Japan
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Tatsuya Tsuzuki,
Tatsuya Tsuzuki
Central Glass Co., Ltd., Matsuzaka, Mie, Japan
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Yasushi Takasaki,
Yasushi Takasaki
Akita University, Akita, Akita, Japan
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Atsushi Shibayama,
Atsushi Shibayama
Akita University, Akita, Akita, Japan
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Tetsuji Yano,
Tetsuji Yano
Tokyo Institute of Technology, Tokyo, Japan
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Masami Nakada,
Masami Nakada
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Yoshihiro Okamoto
Yoshihiro Okamoto
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
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Ippei Amamoto
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Naoki Mitamura
Central Glass Co., Ltd., Matsuzaka, Mie, Japan
Tatsuya Tsuzuki
Central Glass Co., Ltd., Matsuzaka, Mie, Japan
Yasushi Takasaki
Akita University, Akita, Akita, Japan
Atsushi Shibayama
Akita University, Akita, Akita, Japan
Tetsuji Yano
Tokyo Institute of Technology, Tokyo, Japan
Masami Nakada
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Yoshihiro Okamoto
Japan Atomic Energy Agency, Tokai, Ibaraki, Japan
Paper No:
ICEM2010-40272, pp. 503-508; 6 pages
Published Online:
April 5, 2011
Citation
Amamoto, I, Mitamura, N, Tsuzuki, T, Takasaki, Y, Shibayama, A, Yano, T, Nakada, M, & Okamoto, Y. "Removal of Fission Products in the Spent Electrolyte Using Iron Phosphate Glass as a Sorbent." Proceedings of the ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management, Volume 2. Tsukuba, Japan. October 3–7, 2010. pp. 503-508. ASME. https://doi.org/10.1115/ICEM2010-40272
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