Synthesis, structural transformation and magnetic properties of the Nd(III)-doped Fe3−xNd x O4 (0 ≤ x ≤ 0.9): an analogue for actinicles immobilization
Abstract
Magnetite (Fe3O4) is increasingly valued for its excellent performance on radioactive wastes disposal. Here, Fe3−xNd x O4 (0 ≤ x ≤ 0.9) components are synthesized using a co-precipitation method to simulate the solidification capacity for trivalent actinides in Fe3O4. These components are characterized by X-ray diffraction, X-ray photoelectron spectroscopy, Fourier transform infrared spectroscopy and Raman, demonstrating that with the increasement of Nd(III) content, the samples gradually transformed from inverse spinel to orthorhombic phase. And x ≤ 0.6, Nd(III) can be solidified to Fe3O4 lattice via replacing octahedron Fe(III). Furthermore, the vibrating sample magnetometer tests manifest that Fe3−xNd x O4 (0 ≤ x ≤ 0.9) components hold the capable of responding to external magnetic field, which makes magnetic separation feasible. Our findings are expected to provide a promising idea for radioactive wastes disposal.
Funding source: National Natural Science Foundation of China
Award Identifier / Grant number: 20802170
Acknowledgments
We thank Dr. Wei Zhang, Dr. Ruishi Xie, Dr. Xiufang Qi and Dr. Ru Jia for assistance with ICP, XRD, FT-IR and Raman. This work was supported by National Natural Science Foundation of China (20802170).
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Research ethics: Not applicable.
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Informed consent: Not applicable.
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Author contributions: Zaihong Wang and Yongheng Lu designed the study. Zhenfang Cai and Yabin He performed the Nd(III)-doped Fe3−x NdxO4 (0 ≤ x ≤ 0.9) experiments. Zaihong Wang analysed the data. Yiqiang Sun characterized samples with ICP, XRD, FT-IR and Raman. Zaihong Wang, Yongheng Lu, Zhenfang Cai, Yabin He and Yiqiang Sun wrote the paper and discussed the results and commented on the manuscript.
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Use of Large Language Models, AI and Machine Learning Tools: None declared.
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Conflict of interest: None declared.
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Research funding: This work was supported by National Natural Science Foundation of China (20802170).
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Data availability: Not applicable.
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Articles in the same Issue
- Frontmatter
- Comprehensive review of surface contamination in nuclear waste waters: identification, quantification, and mitigation strategies
- Methodology of probabilistic safety assessment for transportation of radioactive material
- A new approach to determine abnormality of radioactive discharges from pressurized water reactors and to derive abnormality indicators correlated with a specific causal event
- A critical analysis of the role of artificial intelligence and machine learning in enhancing nuclear waste management
- Design study of gas-cooled fast reactor with natural uranium as fuel employing modified CANDLE shuffling strategy in the axial direction
- Synthesis, structural transformation and magnetic properties of the Nd(III)-doped Fe3−xNd x O4 (0 ≤ x ≤ 0.9): an analogue for actinicles immobilization
- Examination of the use of thorium-based fuel for burning minor actinides in European sodium cooled fast reactor
- Solitary wave form of reaction rate in graphite diffusive medium using different neutron absorbers
- Evaluation of the unavailability of the primary circuit of Triga SSR reactor, importance factors and risk criteria for its components
- Thermal-hydraulic simulation of loss of flow accident for WWR-S research reactor
- A quick parameter configuration tool for SCHISM’s ocean transport simulation of radioactive materials
- Main heat transport system configuration influence on steam drum level control and safety for a pressure tube type boiling water reactor with multiple interconnected loops
- Testing the thermal performance of water cooling towers
- Design a robust intelligent power controller for pressurized water reactor using particle swarm optimization algorithm
- Calendar of events
Articles in the same Issue
- Frontmatter
- Comprehensive review of surface contamination in nuclear waste waters: identification, quantification, and mitigation strategies
- Methodology of probabilistic safety assessment for transportation of radioactive material
- A new approach to determine abnormality of radioactive discharges from pressurized water reactors and to derive abnormality indicators correlated with a specific causal event
- A critical analysis of the role of artificial intelligence and machine learning in enhancing nuclear waste management
- Design study of gas-cooled fast reactor with natural uranium as fuel employing modified CANDLE shuffling strategy in the axial direction
- Synthesis, structural transformation and magnetic properties of the Nd(III)-doped Fe3−xNd x O4 (0 ≤ x ≤ 0.9): an analogue for actinicles immobilization
- Examination of the use of thorium-based fuel for burning minor actinides in European sodium cooled fast reactor
- Solitary wave form of reaction rate in graphite diffusive medium using different neutron absorbers
- Evaluation of the unavailability of the primary circuit of Triga SSR reactor, importance factors and risk criteria for its components
- Thermal-hydraulic simulation of loss of flow accident for WWR-S research reactor
- A quick parameter configuration tool for SCHISM’s ocean transport simulation of radioactive materials
- Main heat transport system configuration influence on steam drum level control and safety for a pressure tube type boiling water reactor with multiple interconnected loops
- Testing the thermal performance of water cooling towers
- Design a robust intelligent power controller for pressurized water reactor using particle swarm optimization algorithm
- Calendar of events