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Synergy of pyrophosphate and unsaturated nitrogen sites for efficient uranium recovery from concentrated nitric acid

Journal 2025 · IF 15.7 · 16(1): 1-11 · 发表于 2025 年 10 月 17 日
作者: Jian Yaping,Zhang Jiacheng,Cao Xuewen,Peng Qin,Zhang Jun,Tian Xuefeng,Du Jianfei,Li Yan,Yuan Yihui,Wang Ning
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摘要

Efficient recovery of uranium from spent nuclear fuel (SNF) reprocessing in ultra-acidic and radiation-intensive environments is critical for sustainable uranium resources management. However, traditional extractants exhibit instability and reduced uranium adsorption capacity under such harsh conditions. Here, we present a metal-free pyrophosphate-incorporated g-C₃N₄ polymer (PCN x ) featuring unsaturated nitrogen sites and pyrophosphate groups for robust uranyl ion coordination. The inherent stability of g-C 3 N 4 endows PCN x with high resistance to concentrated 12 M HNO 3 and 500 kGy radiation. The optimal PCN 1/3 achieves an uranium adsorption capacity of 75.3 mg g −1 in 12 M HNO 3 and a high removal efficiency of 79.1% in a mixed ion solution, with a high distribution coefficient ( K d ) of 18,964 mL g −1 . This study demonstrates a promising proof-of-concept for designing functional polymers that efficiently recovers uranium from ultra-acidic and radiation-intensive conditions during SNF reprocessing.

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