- 영문명
- 발행기관
- 한국방사성폐기물학회
- 저자명
- Jianan Liu Shinya Nagasaki Tianxiao (Tammy) Yang
- 간행물 정보
- 『Journal of Nuclear Fuel Cycle and Waste Technology (JNFCWT)』Vol.23 No.2, 281~295쪽, 전체 15쪽
- 주제분류
- 공학 > 공학일반
- 파일형태
- 발행일자
- 2025.06.30
4,600원
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국문 초록
The sorption of Europium(III) (Eu(III)) on MX-80 bentonite and granite was systematically studied as a function of ionic strength (0.05-1 mol·kgw−1) and pHm (4-9) in Ca-Na-Cl solutions by batch experiments and 2-site protolysis no electrostatics surface complexation and cation exchange (2SPNE/CE) model. Eu(III) has often been used as a chemical analogue of plutonium(III) which is an important element of interest for the safety assessment of a deep geological repository (DGR) for nuclear waste. It was found that the sorption of Eu(III) on MX-80 and granite was dependent on pHm. The sorption of Eu(III) on MX-80 was dependent on ionic strength at pHm ≤ 6. The effect of ionic strength on the sorption of Eu(III) on granite was negligible. The 2SPNE/CE model simulation suggested that the ion exchange reaction might be the main sorption mechanism at low pHm, while the surface complexation reactions might be the dominant sorption mechanism at higher pHm for the sorption of Eu(III) on both MX-80 and granite.
영문 초록
목차
1. Introduction
2. Experimental Section
3. Results and Discussion
4. Conclusion
Conflict of Interest
Acknowledgements
REFERENCES
해당간행물 수록 논문
- Sorption of Eu(III) Onto MX-80 and Granite in Ca-Na-Cl Solutions
- Comparison of Optimization Algorithms for Fracture Parameters Estimation of Spent Nuclear Fuel Cladding With Reoriented Hydride
- Investigation of the Effect of Wear and Oxidation on the Fatigue Strength Degradation of Zircaloy Cladding Tubes for Spent Nuclear Fuel
- Three-Dimensional Ti3C2Tx (MXene) Film for Radionuclide Removal From an Aqueous Solution
- Development of Reactor Structures Activation Module (RSAM) for Both PWR and CANDU Reactors
- Refined Analytical Method for 129I in Cement-Solidified Spent Ion Exchange Resins
- Impact of Rainfall Patterns on a Near-Surface Radioactive Waste Disposal Facility: Climate Change and Long-Term Perspectives
- A Practical Approach to Structural Evaluation of Radioactive Waste Transport Containers Using Strain Limits Based on Stress Triaxiality
- Pre-Licensing Regulatory Process for Deep Geological Disposal Facility of High-Level Radioactive Waste
- Unconfined Compression Behavior of Unsaturated Compacted Ca-Bentonite: Influence of Ca(OH)2 Solution and Elevated Temperature
참고문헌
- Chem. Rev.
- Nucl. Eng. Des.
- Geochim. Cosmochim. Acta
- Colloids Surf. A: Physicochem. Eng. Asp.
- J. Chem.
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- J. Radioanal. Nucl. Chem.
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- J. Radioanal. Nucl. Chem.
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- Nucl. Eng. Technol.
- Chem. Eng. J.
- Environ. Earth Sci.
- Geochim. Cosmochim. Acta
- J. Radioanal. Nucl. Chem.
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- Geochim. Cosmochim. Acta
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