CTAB modification bentonite for enhanced Re adsorption and diffusion suppression
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Qifeng Jiang
and
Rong Hua
Abstract
99Tc is a crucial high-yield fission product, characterized by its radiotoxicity, extended half-life, high solubility, and significant mobility in the environment. On the other hand, Re is employed as a substitute for Tc due to its analogous properties and non-radioactive nature. Bentonite is commonly used as a backfill material in repositories for high-level radioactive waste storage; however, it exhibits minimal adsorption capacity for Re(Tc). This study aims to enhance the adsorption capability of bentonite for Re(Tc) through modification with Cetyltrimethylammonium Bromide (CTAB). Modified bentonite exhibits excellent adsorption performance under various conditions, primarily driven by the interaction between the ReO4− anion and the pyridinium ring of the CTA+. Its primary adsorption mechanism involves a chemical precipitation reaction between ReO4− and CTA+. The adsorption capacity is approximately 30 times that of unmodified bentonite, and the adsorption process is characterized by spontaneous low-temperature chemical monolayer adsorption. Experimental results of the modification indicate that high-temperature and alkaline modification conditions contribute to enhanced adsorption capacity, with an optimal modification time of approximately 30 h and a maximum modifier addition of 250 % of the bentonite’s cation exchange capacity (CEC). Additionally, the incorporation of modified bentonite into natural bentonite significantly inhibits the diffusion behavior of ReO4−. These findings highlight the substantial improvement in the adsorption capacity of bentonite for Re(Tc) through batch modification, leading to reduced mobility of ReO4− within backfill materials.
Funding source: Key Project of Jiangxi Provincial Natural Science Foundation
Award Identifier / Grant number: 20232ACB203014
Funding source: The Joint Fund of National Key Laboratory – China National Uranium Corporation
Award Identifier / Grant number: 2022NRE-LH-15
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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: Key Project of Jiangxi Provincial Natural Science Foundation (20232ACB203014). The Joint Fund of National Key Laboratory – China National Uranium Corporation (2022NRE-LH-15).
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Data availability: The raw data can be obtained on request from the corresponding author.
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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
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
