A fine crystalline ammonium tungstophosphate (AWP) exchanger with high selectivity toward Cs+ was encapsulated in biopolymer matrices (calcium alginate, CaALG). The characterization of the AWP-CaALG microcapsule was examined using SEM/WDS, IR and DTA/TG analyses, and the selective separation and recovery of 137Cs were examined by the batch and column methods using simulated and real high-level liquid waste (HLLW). The free energy (ΔG0) of the ion exchange ( ↔ Cs+) for fine AWP crystals was determined at −13.2 kJ/mol, indicating the high selectivity of AWP towards Cs+. Spherical and elastic AWP-CaALG microcapsules (∼700 μm in diameter) were obtained and fine AWP crystals were uniformly immobilized in alginate matrices. Relatively large Kd values of Cs+ above 105 cm3/g were obtained in the presence of 10−3∼1 M Ca(NO3)2, resulting in a separation factor of Cs/Rb exceeding 102. The irradiated samples (60Co, 17.6 kGy) also exhibited large Kd values exceeding 105 cm3/g in the presence of 2.5 M HNO3. The Kd values in the presence of 0.1–9 M HNO3 for 67 elements were determined and the order of Kd value was Cs+ ≫ Rb+ > Ag+. The breakthrough curve of Cs+ had an S-shaped profile, and the breakpoint increased with decreasing flow rate; the breakpoint and breakthrough capacity at a flow rate of 0.35 cm3/min for the column (0.7 g AWP-CaALG) were estimated at 25.2 cm3 and 0.068 mmol/g, respectively. Good breakthrough and elution properties were retained even after thrice-repeated runs. The uptake (%) of Cs+ in simulated HLLW (28 metal components-1.92 M HNO3, SW-11, JAEA) was estimated at 97%, and the distribution of Cs+ and Zr/Ru into the AWP and alginate phases, respectively, were observed by WDS analysis. Further, the selective uptake of 137Cs exceeding 99% was confirmed by using real HLLW (FBR “JOYO”, JAEA). The AWP-CaALG microcapsules are thus effective for the selective separation and recovery of Cs+ from HLLWs.
Skip Nav Destination
18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4929-3
PROCEEDINGS PAPER
Selective Separation and Recovery of Cesium by Ammonium Tungstophosphate-Alginate Microcapsules Available to Purchase
Hitoshi Mimura,
Hitoshi Mimura
Tohoku University, Sendai, Japan
Search for other works by this author on:
Yuichi Niibori,
Yuichi Niibori
Tohoku University, Sendai, Japan
Search for other works by this author on:
Isao Yamagishi,
Isao Yamagishi
Japan Atomic Energy Agency, Ibaraki, Japan
Search for other works by this author on:
Masaki Ozawa,
Masaki Ozawa
Japan Atomic Energy Agency, Ibaraki, Japan
Search for other works by this author on:
Takashi Ohnishi,
Takashi Ohnishi
Japan Atomic Energy Agency, Ibaraki, Japan
Search for other works by this author on:
Shinichi Koyama
Shinichi Koyama
Japan Atomic Energy Agency, Ibaraki, Japan
Search for other works by this author on:
Hitoshi Mimura
Tohoku University, Sendai, Japan
Yan Wu
Tohoku University, Sendai, Japan
Yufei Wang
Tohoku University, Sendai, Japan
Yuichi Niibori
Tohoku University, Sendai, Japan
Isao Yamagishi
Japan Atomic Energy Agency, Ibaraki, Japan
Masaki Ozawa
Japan Atomic Energy Agency, Ibaraki, Japan
Takashi Ohnishi
Japan Atomic Energy Agency, Ibaraki, Japan
Shinichi Koyama
Japan Atomic Energy Agency, Ibaraki, Japan
Paper No:
ICONE18-29091, pp. 419-427; 9 pages
Published Online:
April 8, 2011
Citation
Mimura, H, Wu, Y, Wang, Y, Niibori, Y, Yamagishi, I, Ozawa, M, Ohnishi, T, & Koyama, S. "Selective Separation and Recovery of Cesium by Ammonium Tungstophosphate-Alginate Microcapsules." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 1. Xi’an, China. May 17–21, 2010. pp. 419-427. ASME. https://doi.org/10.1115/ICONE18-29091
Download citation file:
16
Views
Related Proceedings Papers
Related Articles
BIO-MANUFACTURING OF ENGINEERED LIVING MATERIALS FOR MARTIAN CONSTRUCTION: DESIGN OF THE SYNTHETIC COMMUNITY
J. Manuf. Sci. Eng (January,0001)
Design of a Membraneless Passive Planar Four-Cell Direct Borohydride Fuel Cell
J. Fuel Cell Sci. Technol (February,2012)
Biomimetics: Advancing Man-Made Materials Through Guidance From Nature - An Update
Appl. Mech. Rev (October,1996)
Related Chapters
Characterization of Irradiation Damage Using X-Ray Diffraction Line-Profile Analysis
Zirconium in the Nuclear Industry: 20th International Symposium
Effect of Grain Dimensions on the Diametral Creep of Zr-2.5Nb Pressure Tubes
Zirconium in the Nuclear Industry: 20th International Symposium
Available High-Purity Materials
Report on Available Standard Samples and Related Materials for Spectrochemical Analysis