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The limited availability of uranium (U) resources poses significant challenges to the advancement of nuclear energy. Recycling uranium from spent fuel is critical, but the coexistence of lanthanides (Ln) complicates the extraction process significantly. Here, we present an N/O ligand, ()-'-(pyridin-2-ylmethylene) picolinohydrazide (), designed for the selective recovery of U(VI) over Ln(III/IV) in acidic environments. 3,6-Bis(2-pyridinyl)-1,2,4,5-tetrazine () and ,-dimethylformamide (), when subjected to heat, gradually generate and formic acid in aqueous solution; this process can be employed for uranium recovery. This approach, known as the in situ reactive extraction technique, enhances capture capacity, selectivity, and acid resistance while effectively mitigating interference from Ce(IV). At pH 3 and 0.1 M HNO, separation factors for the binary Ln(III/IV) and U(VI) systems exceeded 10 and 10, respectively, achieving purities exceeding 99%. Monocrystalline structure analysis revealed two-dimensional planar coordination complexes, demonstrating their exceptional selectivity. This study underscores the potential of in uranium recovery from spent fuel and proposes new avenues for developing innovative separation strategies for lanthanides and actinides (An) using structural and theoretical modeling.
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http://dx.doi.org/10.1021/acs.inorgchem.4c04459 | DOI Listing |
ACS Omega
September 2025
Australian Nuclear Science and Technology Organisation, Locked Bag 2001, Kirrawee DC, NSW 2232, Australia.
We report the hydrothermal syntheses and structural and spectroscopic characterization of two new uranium oxide hydrate frameworks (UOHFs) with either Pr or Nd ions, Pr(HO)[(UO)UO(OH)] () or Nd(HO)[(UO)UO(OH)] (). Both UOHFs crystallize in the orthorhombic 222 space group and display needle crystal morphologies. Their crystal structures are composed of β-UO-type layers connected by double uranium polyhedra to form the frameworks, with disordered Pr/Nd ions within the framework channels, as revealed by synchrotron single-crystal XRD.
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August 2025
School of Materials Science and Engineering, China University of Petroleum (East China), Qingdao 266580, China.
One of the most critical steps in the treatment of spent nuclear fuel is the removal of americium (Am) and curium (Cm) ions from radioactive wastewater. The use of new materials with high surface areas, such as graphene, has been considered a promising solution to this issue. Therefore, understanding the mechanism by which Am and Cm ions are adsorbed onto the graphene surface in aqueous solutions is of paramount importance.
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August 2025
Department of Chemistry and Biochemistry, University of Nevada Las Vegas, 4505 Maryland Parkway, Las Vegas, Nevada 89154, United States.
The formation of Tc-(VII)-Zr-(IV) species in nitric acid and their extraction in kerosene/tributyl phosphate (TBP) phases was studied. The technetium distribution coefficient ( ) was evaluated as a function of nitric acid concentration (1-7 M) and is in the range of 25-37, which is significantly higher compared to solutions that do not contain zirconium and confirms the synergism of their coextraction. Emphasis was placed on 1 M HNO solution, which is the initial concentration used in uranium extraction during spent nuclear fuel reprocessing.
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August 2025
Nuclear Fuel Cycle Research School, Nuclear Science and Technology Research Institute, AEOI, Tehran, 14893-836, Iran.
The superior efficacy of synroc as an immobilization matrix for actinides in spent nuclear fuel has been extensively validated, positioning it as a leading candidate for long-term nuclear waste management. In this context, isotopic investigations of natural analogues are indispensable for optimizing synroc formulations, particularly regarding their capacity to incorporate and retain actinides and their decay products over geological timescales. In this study, a naturally occurring member of the pyrochlore supergroup was identified as betafite through integrated SEM, EMPA, and XRD analyses.
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August 2025
Medical Radiation Physics Malmö, Department of Translational Medicine, Lund University Skåne University Hospital Malmö, SUS Malmö, Inga Maria Nilssons gata 47, SE-205 02 Malmö, Sweden.
Carbon-14 often dominates the effective dose to the public from authorized discharges from Swedish nuclear power plants (NPPs). In contrast to air-borne releases, water-borne discharges of 14C are currently not routinely monitored at Swedish NPPs. We have measured 14C in Fucus spp.
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