DGA-grafting pyridine for ultra-selective and prior extraction of 99TcO4− from simulated spent nuclear fuel
Selective and prior extraction of <sup>99</sup>TcO<sub>4</sub><sup>-</sup> ahead of uranium and plutonium separation is a beneficial strategy for the modern nuclear fuel cycle. Herein, a novel DGA-grafting pyridine ligand BisDODGA-DAPy (L1) was tailored for the efficient separation of TcO<sub>4</sub><sup>-</sup> from simulated spent nuclear fuel based on the selectivity of pyridine and synergistic effect of diglycolamide (DGA) group. Compared to the ligands BisDOSCA-DAPy (L2) and BisDODGA-MPDA (L3) with similar structure, BisDODGA-DAPy (L1) demonstrated the better separation performance including good extraction efficiency, reusability, and high loading capacity for TcO<sub>4</sub><sup>-</sup> under high acidic medium. The interactions of the ligands with Tc(VII)/Re(VII) have been investigated in detail using FT-IR, <sup>1</sup>H NMR titration, UV-Vis spectrophotometric titration, ESI-HRMS and DFT simulations. The extraction mechanism affected by the protonation of ligand was elucidated under different acidity. BisDODGA-DAPy (L1) demonstrated the ultra-selective extraction ability for TcO<sub>4</sub><sup>-</sup> from simulated spent nuclear fuel. The maximum SF<sub>Tc/U</sub> and SF<sub>Tc/Pu</sub> values were up to 1.29 × 10<sup>4</sup> and 5.08 × 10<sup>3</sup>, respectively. In the presence of 9 × 10<sup>4</sup>-fold excess of NO<sub>3</sub><sup>-</sup>, the extraction of TcO<sub>4</sub><sup>-</sup> was almost unaffected. Moreover, the good radiolytic stability further highlights the promising potential of this ligand for <sup>99</sup>Tc separation. DFT calculation revealed the dominant role of DAPy and DODGA in TcO<sub>4</sub><sup>-</sup> extraction, providing the theoretical evidence for BisDODGA-DAPy (L1) to selectively bind TcO<sub>4</sub><sup>-</sup> over NO<sub>3</sub><sup>-</sup>.
Authors
- Wenya Tai
- Ze‐Yi Yan (ORCID: https://orcid.org/0000-0001-9368-420X)
- Xiaopei Qi
- Qiang Wu (ORCID: https://orcid.org/0000-0002-5645-4883)
- Fei Wu (ORCID: https://orcid.org/0000-0002-8068-3117)
- Huaixin Hao (ORCID: https://orcid.org/0000-0002-5815-469X)
- Weijia Wang (ORCID: https://orcid.org/0000-0003-0602-8162)
- Zhipeng Wang (ORCID: https://orcid.org/0000-0002-7849-9556)
Institutions
- Lanzhou University of Technology (CN)
- Lanzhou University (CN)
- Tsinghua University (CN)
Publication Details
- Journal
- Journal of Hazardous Materials
- Published
- 2024-08-05
- DOI
- https://doi.org/10.1016/j.jhazmat.2024.135435
- Citations
- 10
- Primary Topic
- Radioactive element chemistry and processing
- Type
- article
- Field-Weighted Citation Impact
- 1.58
Funders
- National Natural Science Foundation of China