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Experimental and numerical investigations of 99TcO4− diffusion in compacted SPV 200 bentonite

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Abstract

Diffusion characteristics in bentonite are essential to quantify the transport of radionuclides through buffer/backfill materials in waste repositories. This study employs through-diffusion techniques to investigate the diffusion behavior of 99TcO4− through SPV bentonite with various densities. The apparent diffusion coefficients for bentonite densities are estimated using Marquardt–Levenberg optimization algorithm in the HYDRUS-1D model. Based on the experimental and calculation results, 99Tc could be considered as non-sorbing radionuclides. The data obtained in this study provide a valuable reference for the safety assessment of waste repositories.

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Acknowledgements

This work was financially supported by the Nuclear Backend Management Department at Taiwan Power Company.

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Authors and Affiliations

  1. Chemistry Division, Institute of Nuclear Energy Research, No. 1000, Wenhua Rd., Jiaan Village, Longtan District, Taoyuan City, 32546, Taiwan

    Yu-Hung Shih, Tsuey-Lin Tsai, Liang-Cheng Chen & Te-Yen Su

  2. Center for Environmental Studies, National Central University, No. 300, Zhongda Rd., Zhongli Dist., Taoyuan City, 320, Taiwan

    I-Hsien Lee & Chuen-Fa Ni

  3. Graduate Institute of Applied Geology, National Central University, No. 300, Zhongda Rd., Zhongli Dist., Taoyuan City, 320, Taiwan

    Chuen-Fa Ni

  4. Department of Earth Sciences, National Cheng Kung University, Tainan City, No.1, University Road, 70101, Taiwan

    Chuan-Pin Lee

  5. Nuclear Science and Technology Development Center, National Tsing Hua University, Hsinchu, 30013, Taiwan

    Shih-Chin Tsai

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  1. Yu-Hung Shih
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Correspondence to I-Hsien Lee.

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Shih, YH., Lee, IH., Ni, CF. et al. Experimental and numerical investigations of 99TcO4− diffusion in compacted SPV 200 bentonite. J Radioanal Nucl Chem 316, 1081–1089 (2018). https://doi.org/10.1007/s10967-018-5800-x

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  • DOI: https://doi.org/10.1007/s10967-018-5800-x

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