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

Yu Hung Shih; I. Hsien Lee; Chuen Fa Ni; Tsuey Lin Tsai; Liang Cheng Chen; Chuan Pin Lee; Shih Chin Tsai; Te Yen Su

doi:10.1007/s10967-018-5800-x

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

Yu Hung Shih, I. Hsien Lee, Chuen Fa Ni, Tsuey Lin Tsai, Liang Cheng Chen, Chuan Pin Lee, Shih Chin Tsai, Te Yen Su

Department of Earth Sciences

Research output: Contribution to journal › Article › peer-review

6 Citations (Scopus)

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.

Original language	English
Pages (from-to)	1081-1089
Number of pages	9
Journal	Journal of Radioanalytical and Nuclear Chemistry
Volume	316
Issue number	3
DOIs	https://doi.org/10.1007/s10967-018-5800-x
Publication status	Published - 2018 Jun 1

All Science Journal Classification (ASJC) codes

Analytical Chemistry
Nuclear Energy and Engineering
Radiology Nuclear Medicine and imaging
Pollution
Spectroscopy
Public Health, Environmental and Occupational Health
Health, Toxicology and Mutagenesis

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

Access to Document

10.1007/s10967-018-5800-x

Cite this

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title = "Experimental and numerical investigations of 99TcO4 − diffusion in compacted SPV 200 bentonite",

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.",

author = "Shih, {Yu Hung} and Lee, {I. Hsien} and Ni, {Chuen Fa} and Tsai, {Tsuey Lin} and Chen, {Liang Cheng} and Lee, {Chuan Pin} and Tsai, {Shih Chin} and Su, {Te Yen}",

note = "Funding Information: Acknowledgements This work was financially supported by the Nuclear Backend Management Department at Taiwan Power Company. Publisher Copyright: {\textcopyright} 2018, Akad{\'e}miai Kiad{\'o}, Budapest, Hungary.",

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doi = "10.1007/s10967-018-5800-x",

language = "English",

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T1 - Experimental and numerical investigations of 99TcO4 − diffusion in compacted SPV 200 bentonite

AU - Shih, Yu Hung

AU - Lee, I. Hsien

AU - Ni, Chuen Fa

AU - Tsai, Tsuey Lin

AU - Chen, Liang Cheng

AU - Lee, Chuan Pin

AU - Tsai, Shih Chin

AU - Su, Te Yen

N1 - Funding Information: Acknowledgements This work was financially supported by the Nuclear Backend Management Department at Taiwan Power Company. Publisher Copyright: © 2018, Akadémiai Kiadó, Budapest, Hungary.

PY - 2018/6/1

Y1 - 2018/6/1

N2 - 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.

AB - 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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