Investigating advection–dispersion behavior for simulation of HTO and 238Pu transport in argillaceous shale with different varying degrees of weathering
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Yunfeng Shi
and
Bing Lian
Abstract
Exploring the migration behavior of radioactive nuclides in the surrounding rock media of the disposal site is the basis for the safety evaluation of radioactive waste disposal sites. In this study, the column experiment was employed to evaluate the nuclide migration behavior in the surrounding rock medium of a near-surface disposal site in China and to investigate the advection–dispersion behavior of tritium (HTO) and plutonium-238 (238Pu) in highly weathered argillaceous shale with different degree of weathering. A reasonable numerical model was selected to fit the experimental breakthrough curves (BTCs) and obtain relevant migration parameters. The results showed that: (1) the breakthrough curves of HTO and 238Pu in fractured media with varying degrees of weathering exhibited clear “peak forward” and “tail dragging” phenomena; (2) the stream tube model can better fit the BTCs of the nuclides in the highly weathered fractures and obtain the average dispersion coefficient <D>, average distribution coefficient <K d>, and other parameters; (3) the two-region non-equilibrium model can better fit the BTCs of the nuclides in the penetrating fractures and weak weathering fractures and obtain the volumetric water content of the mobile liquid region (θ m), distribution coefficient (K d), and other parameters.
Award Identifier / Grant number: No. SN22010301
Funding source: State Key Laboratory for Nuclear Resources and Environment, East China Institute of Technology
Award Identifier / Grant number: No. 2022RGET02
Funding source: The National Natural Science Foundation of China
Award Identifier / Grant number: No. U2267218
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Research ethics: Not applicable.
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Author contributions: The authors have accepted responsibility for the entire content of this manuscript and approved its submission.
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Competing interests: The authors state no conflict of interest.
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Research funding: This project was mainly supported by the Fundamental Science on Radioactive Geology and Exploration Technology Laboratory (State Key Laboratory for Nuclear Resources and Environment, East China Institute of Technology, https://doi.org/10.13039/501100020742) (No. 2022RGET02), East China University of Technology, Shanxi Province (Natural Science Foundation for Young Scientists of Shanxi Province, https://doi.org/10.13039/501100020771) Basic research Project (No. SN22010301), The National Natural Science Foundation of China (No. U2267218).
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Data availability: The raw data can be obtained on request from the corresponding author.
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- Calendar of events
Articles in the same Issue
- Frontmatter
- Numerical study on the effect of the PI-controller type on the quasi-steady reactor pressure in MAAP 5.04 code
- Analyses of the unavailability dynamics of emergency core cooling system
- Study on spent fuel heatup during spent fuel pool complete loss of coolant accident
- Numerical simulation analysis of high-temperature bent sodium heat pipes
- Influence of the twisting and nano fluids on performance of a triangular double tube heat exchanger
- Neutronic simulation of Traveling Wave Reactor (TWR) core in multi-cycles using Monte Carlo method
- Gain scheduled internal model control based on the dynamic sliding mode method for the water level of nuclear steam generators
- Verification and validation optimization method for signal quality bits in digital control system application software of nuclear power plant
- Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor
- A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis
- CTAB modification bentonite for enhanced Re adsorption and diffusion suppression
- Study on advection–dispersion behavior for simulation of 3H, 99Tc, and 90Sr transport in crushed sandstone of column experiments
- Investigating advection–dispersion behavior for simulation of HTO and 238Pu transport in argillaceous shale with different varying degrees of weathering
- Study on analysing the potential benefits of utilizing nuclear waste for biodiesel production
- Calendar of events
