학술논문
Hydraulic Conductivity of Compact Bentonite With Penetrating Copper Pins
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- 영문명
- 발행기관
- 한국방사성폐기물학회
- 저자명
- Min Soo Lee Min Seop Kim Seok Yoon Jin Seop Kim
- 간행물 정보
- 『Journal of Nuclear Fuel Cycle and Waste Technology (JNFCWT)』Vol.23 No.3, 415~422쪽, 전체 8쪽
- 주제분류
- 공학 > 공학일반
- 파일형태
- 발행일자
- 2025.09.30
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국문 초록
Copper plates are a proposed engineering solution to enhance thermal dissipation from nuclear waste canisters through the surrounding bentonite buffer. However, their long-term effect on the hydraulic integrity of this bentonite buffer is uncertain. This study experimentally investigates the impact of penetrating copper components on the hydraulic conductivity of compact bentonite. We measured the hydraulic conductivity of bentonite blocks penetrated by 0 (control), 5, and 10 copper pins, both at initial saturation and after a 293-day aging period. Initially, hydraulic conductivity decreased from 1.49 × 10⁻13 m·s−1 in the control as the number of pins increased. However, this monotonic trend did not persist; after 293 days, the relationship became non-linear, with the 5-pin block showing the lowest conductivity and the 10-pin block the highest. Crucially, our findings provide no evidence that copper penetration or subsequent corrosion systematically increases hydraulic conductivity. We conclude that the integration of copper plates for thermal management is unlikely to compromise the critical containment function of the bentonite barrier.
영문 초록
목차
1. Introduction
2. Materials and Methods
3. Result and Discussions
4. Conclusion
Conflict of Interest
Acknowledgements
REFERENCES
해당간행물 수록 논문
- Journal of Nuclear Fuel Cycle and Waste Technology (JNFCWT) Vol.23 No.3 Contents
- Time-Dependent Safety Analysis of Spent Nuclear Fuel: An MCNPX- MATLAB Framework Linking Isotopic Predictions to Phase-Dominant Contributions in Decay Heat and Radioactivity
- Assessment of Radionuclide Inventory Distribution Characteristics in the Bioshield Concrete of a PWR Reactor
- Evaluation of Nonlinear and Polynomial Efficiency Models Based on Triple-to-Double Coincidence Ratio in Liquid Scintillation Counting
- Statistical Methodology for Uncertainty Evaluation in Efficiency Calibration of Liquid Scintillation Counting: Case Study With Tritium
- Fabrication and Characterization of Cement Re-Solidified Form for Historic Boron Concentrates
- Development of Evaluation System for Long-Term Aging Management of Internal Structural Materials in Dry Storage Systems
- Design and Thermal Optimization of a Microwave Reactor Crucible for Radioactive Carbon Treatment
- Evaluation of Cement Waste Form for Final Disposal of Uranium Contained Wastes
- Structural Evaluation of Storage Racks According to Seismic Impact in SFP
- Hydraulic Conductivity of Compact Bentonite With Penetrating Copper Pins
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공학 > 공학일반분야 NEW
- Journal of Nuclear Fuel Cycle and Waste Technology (JNFCWT) Vol.23 No.3 Contents
- Time-Dependent Safety Analysis of Spent Nuclear Fuel: An MCNPX- MATLAB Framework Linking Isotopic Predictions to Phase-Dominant Contributions in Decay Heat and Radioactivity
- Assessment of Radionuclide Inventory Distribution Characteristics in the Bioshield Concrete of a PWR Reactor
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