In this study, a simulated ammonium diuranate filtrate (ADUF) which was obtained by adding uranyl nitrate to a 35 g/L ammonium nitrate solution to adjust the uranium concentration to about 50 mg/L was treated by a nanofiltration process. Experiments were carried out on a plate membrane testing device with a trans-membrane pressure (TMP) range of 0.5 ∼ 3.0 MPa, a crossflow velocity range of 10 ∼ 50 cm/s and a temperature range of 5 ∼ 35 °C. The results show that NF270 membrane has good rejection property for uranium and excellent permeability for ammonium nitrate. The ammonium nitrate concentration in the permeate is about 32 g/L which means the reject ratio of ammonium nitrate is only about 10%. Though NF270 membrane shows good uranium rejection property, the corresponding permeate flux is very high. When the trans-membrane pressure is 1.5 MPa, the uranium reject ratio is 96.8% and the the corresponding permeate flux is about 80 L/(m2·h). It indicates a bright application prospect of nanofiltration process in the treatment of ADUF.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5785-4
PROCEEDINGS PAPER
The Removal of Uranium From Simulated Ammonium Diuranate Filtrate by Nanofiltration Available to Purchase
Yuan Zhongwei,
Yuan Zhongwei
China Institute of Atomic Energy, Beijing, China
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Wang Runci,
Wang Runci
China Institute of Atomic Energy, Beijing, China
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Yan Taihong,
Yan Taihong
China Institute of Atomic Energy, Beijing, China
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Zheng Weifang
Zheng Weifang
China Institute of Atomic Energy, Beijing, China
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Yuan Zhongwei
China Institute of Atomic Energy, Beijing, China
Wang Runci
China Institute of Atomic Energy, Beijing, China
Yan Taihong
China Institute of Atomic Energy, Beijing, China
Zheng Weifang
China Institute of Atomic Energy, Beijing, China
Paper No:
ICONE25-67899, V007T10A042; 5 pages
Published Online:
October 17, 2017
Citation
Zhongwei, Y, Runci, W, Taihong, Y, & Weifang, Z. "The Removal of Uranium From Simulated Ammonium Diuranate Filtrate by Nanofiltration." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events. Shanghai, China. July 2–6, 2017. V007T10A042. ASME. https://doi.org/10.1115/ICONE25-67899
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