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Migration study of uranium in Beishan granite by the continuous column method

  • Siyi Gong , Jinguang Zheng , Xin Yang , Yan Ma , Zhenfeng Tong and Tao Chen EMAIL logo
Published/Copyright: June 5, 2024
Radiochimica Acta
From the journal Radiochimica Acta Volume 112 Issue 10

Abstract

Radionuclide migration is an essential process in the performance and safety assessments of radioactive waste repository. This study investigates uranium migration in Beishan granite using the continuous column method, focusing on the effects of flow rate, eluent pH, and carbonate. Experimental parameters were used to perform COMSOL simulations of the migration process. The findings reveal that mechanical dispersion plays a predominant role in uranium migration in the granite column. Notably, the impact of adsorption on migration appears to be limited, likely due to the brief contact time in the experimental setup. The study successfully demonstrates the capability of COMSOL in simulating radionuclide migration, offering significant insights for the performance and safety assessments of repository.

Keywords: uranium; granite; migration parameters; continuous column method; COMSOL
Corresponding author: Tao Chen, School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China, E-mail:

Funding source: National Natural Science Foundation of China

Award Identifier / Grant number: Unassigned

Funding source: Fundamental Research Funds for the Central Universities

Award Identifier / Grant number: Unassigned

Acknowledgments

This work was financially supported by the National Natural Science Foundation of China (12275083) and the Fundamental Research Funds for the Central Universities (2022MS040).

  1. Research ethics: Safety assessment of radioactive waste repository, radionuclide migration.

  2. Author contributions: The authors have accepted responsibility for the entire content of this manuscript and approved its submission.

  3. Competing interests: The authors state no conflict of interest.

  4. Research funding: National Natural Science Foundation of China (U1967212) Fundamental Research Funds for the Central Universities (2022MS040).

  5. Data availability: The raw data can be obtained on request from the corresponding author.

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Received: 2024-01-30
Accepted: 2024-05-22
Published Online: 2024-06-05
Published in Print: 2024-10-28

© 2024 Walter de Gruyter GmbH, Berlin/Boston

Articles in the same Issue

  1. Frontmatter
  2. Original Papers
  3. Migration study of uranium in Beishan granite by the continuous column method
  4. Process development studies on the recovery of caesium specific calix-crown-6 extractant from actual spent calix solution for efficient spent solvent management
  5. Evaluating SiO2/Al2O3/poly(acrylic acid-co-glycidyl methacrylate) composite as a novel adsorbent for cobalt(II) radionuclides
  6. Investigation of radioactivity concentrations and soil-to-plant transfer factors in soil samples taken from different distance zones to the Metsamor nuclear power plant
  7. Sorption behavior of low specific activity 99Mo on Ti- and Zr-xerogels as an alternative to fission-based 99Mo/99mTc generators
  8. Application of INAA technique for analysis of essential and toxic elements in two Algerian plants Cynodon dactylon L. and Phragmites australis
  9. Hydrodynamic study of a flow-rig column by means of a radiotracer technique modelling with DTS-Pro 4
  10. On transfer factors of natural radionuclides and radiological health risks assessment of some fruit samples
  11. New lead barium borate glass system for radiation shielding applications: impacts of copper (II) oxide on physical, mechanical, and gamma-ray attenuation properties
https://doi.org/10.1515/ract-2024-0281
Keywords for this article
uranium; granite; migration parameters; continuous column method; COMSOL

Articles in the same Issue

  1. Frontmatter
  2. Original Papers
  3. Migration study of uranium in Beishan granite by the continuous column method
  4. Process development studies on the recovery of caesium specific calix-crown-6 extractant from actual spent calix solution for efficient spent solvent management
  5. Evaluating SiO2/Al2O3/poly(acrylic acid-co-glycidyl methacrylate) composite as a novel adsorbent for cobalt(II) radionuclides
  6. Investigation of radioactivity concentrations and soil-to-plant transfer factors in soil samples taken from different distance zones to the Metsamor nuclear power plant
  7. Sorption behavior of low specific activity 99Mo on Ti- and Zr-xerogels as an alternative to fission-based 99Mo/99mTc generators
  8. Application of INAA technique for analysis of essential and toxic elements in two Algerian plants Cynodon dactylon L. and Phragmites australis
  9. Hydrodynamic study of a flow-rig column by means of a radiotracer technique modelling with DTS-Pro 4
  10. On transfer factors of natural radionuclides and radiological health risks assessment of some fruit samples
  11. New lead barium borate glass system for radiation shielding applications: impacts of copper (II) oxide on physical, mechanical, and gamma-ray attenuation properties
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