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Comparison of modeling methods for the effective diffusivities of IO3− estimated in compacted bentonite using through-diffusion tests under aerobic conditions

  • Tsuey-Lin Tsai and Shih-Chin Tsai ORCID logo EMAIL logo
Published/Copyright: July 26, 2024
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Kerntechnik
From the journal Kerntechnik Volume 89 Issue 4

Abstract

Diffusion is the predominant mechanism governing the transport of 129I through geosphere. Consequently, the assessment of the experimental findings on two-compartment diffusion reservoirs of IO3− within compacted bentonite involved the application of three distinct diffusion models: CC–CC (constant concentration), CC–VC (variable concentration), and VC–VC. To ensure the reliability of the obtained diffusion coefficients, multiple laboratory tests were performed for internal comparison. The experimental results revealed that IO3− diffusion coefficients were ranging from 3.83 × 10−13 to 1.91 × 10−11  m2/s. These techniques using three mathematical models could be conducted to estimate the diffusion coefficients of non- or weakly-sorbing radionuclides on compacted bentonite for safety assessment of radioactive waste final disposal.

Keywords: through-diffusion; bentonite; diffusion coefficient; mathematical model; non-sorbing radionuclide
Corresponding author: Shih-Chin Tsai, Nuclear Science and Technology Development Center, National Tsing Hua University, Hsinchu 30013, Taiwan, E-mail:

Acknowledgments

The authors would like to thank the researchers at the Radioactive Waste Disposal Technology Research and Development Center, National Tsing Hua University for technical discussions.

  1. Research ethics: Not applicable.

  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: The Science and Technology Development Fund supported this project under contract number NSTC 113-2623-E-007-006-NU.

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

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Received: 2024-02-16
Accepted: 2024-06-12
Published Online: 2024-07-26
Published in Print: 2024-08-27

© 2024 Walter de Gruyter GmbH, Berlin/Boston

Articles in the same Issue

  1. Frontmatter
  2. Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor
  3. Comparison of modeling methods for the effective diffusivities of IO3− estimated in compacted bentonite using through-diffusion tests under aerobic conditions
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  8. System theory safety analysis of network malfunction in nuclear power plant distributed control systems
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  10. Methodology for analyzing dose consequence using atmospheric dispersion code A2CDOSE
  11. Reliability analysis of digital reactor protection systems in floating nuclear power plants
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  14. Calendar of events
https://doi.org/10.1515/kern-2024-0016
Keywords for this article
through-diffusion; bentonite; diffusion coefficient; mathematical model; non-sorbing radionuclide

Articles in the same Issue

  1. Frontmatter
  2. Multilateral evaluation of the effects of utilizing thorium oxide in the Bushehr VVER-1000 reactor
  3. Comparison of modeling methods for the effective diffusivities of IO3− estimated in compacted bentonite using through-diffusion tests under aerobic conditions
  4. Analysis of initial core and time dependent fuel burnup for high temperature testing reactors (HTTRs)
  5. A detection and defense security system design for nuclear waste storage against stealth terrorists attack
  6. Optimization of ECR assisted pre-ionization in GLAST-III via Multiphysics simulation
  7. Fuzzy reliability algorithm for the shutdown system of research reactor
  8. System theory safety analysis of network malfunction in nuclear power plant distributed control systems
  9. Two phase flow analysis of micro channel evaporator to investigate effect of geometry on pressure and heat transfer coefficient with respect to volume of fraction
  10. Methodology for analyzing dose consequence using atmospheric dispersion code A2CDOSE
  11. Reliability analysis of digital reactor protection systems in floating nuclear power plants
  12. Study on comprehensive evaluation method of mental workload level
  13. Integrating reliability analysis into MBSE for FPGA-based safety critical I&C system design in nuclear power plants
  14. Calendar of events
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