TY - JOUR
T1 - Diffusion characteristics of HTO and 99TcO4 - In compacted Gaomiaozi (GMZ) bentonite
AU - Tsai, Tsuey Lin
AU - Tsai, Shih Chin
AU - Shih, Yu Hung
AU - Chen, Liang Cheng
AU - Lee, Chuan Pin
AU - Su, Te Yen
N1 - Funding Information:
The authors would like to thank the Nuclear Backend Management Department at Taiwan Power Company for financially supporting this research.
Publisher Copyright:
© 2017 Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Chinese Nuclear Society, Science Press China and Springer Science+Business Media Singapore.
PY - 2017/5/1
Y1 - 2017/5/1
N2 - The characteristics of diffusion are essential to the transport of radionuclides through buffer/backfill materials, such as bentonite, which are commonly found in waste repositories. This study used through-diffusion techniques to investigate the diffusion behavior of HTO and 99TcO4 - on GMZ bentonite of various densities. Diffusion rates were calculated by measuring the diffusion coefficients (D e, D a), plotting breakthrough curves and interpreting experiment data. The apparent and effective diffusion coefficients of HTO ranged from (1.68 ± 0.40) × 10-11 to (2.80 ± 0.62) × 10-11 m2/s and from (4.61 ± 1.28) × 10-12 to (16.2 ± 2.50) × 10-12 m2/s, respectively. The apparent and effective diffusion coefficients of 99TcO4 - ranged from (5.26 ± 0.16) × 10-12 to (7.78 ± 0.43) × 10-12 m2/s and from (1.49 ± 0.002) × 10-12 to (4.16 ± 0.07) × 10-12 m2/s, respectively. The distribution coefficients of HTO and 99TcO4 - ranged from (0.70 ± 0.12) × 10-2 to (1.36 ± 0.53) × 10-2 mL/g and from (1.12 ± 0.06) × 10-2 to (5.79 ± 2.22) × 10-2 mL/g, respectively. The D e and K d values were shown to decrease with an increase in the bulk dry density of compacted bentonite. Our results show that HTO and 99Tc could be considered non-sorbent radionuclides. The data obtained in this study provide a valuable reference for the safety assessment of waste repositories.
AB - The characteristics of diffusion are essential to the transport of radionuclides through buffer/backfill materials, such as bentonite, which are commonly found in waste repositories. This study used through-diffusion techniques to investigate the diffusion behavior of HTO and 99TcO4 - on GMZ bentonite of various densities. Diffusion rates were calculated by measuring the diffusion coefficients (D e, D a), plotting breakthrough curves and interpreting experiment data. The apparent and effective diffusion coefficients of HTO ranged from (1.68 ± 0.40) × 10-11 to (2.80 ± 0.62) × 10-11 m2/s and from (4.61 ± 1.28) × 10-12 to (16.2 ± 2.50) × 10-12 m2/s, respectively. The apparent and effective diffusion coefficients of 99TcO4 - ranged from (5.26 ± 0.16) × 10-12 to (7.78 ± 0.43) × 10-12 m2/s and from (1.49 ± 0.002) × 10-12 to (4.16 ± 0.07) × 10-12 m2/s, respectively. The distribution coefficients of HTO and 99TcO4 - ranged from (0.70 ± 0.12) × 10-2 to (1.36 ± 0.53) × 10-2 mL/g and from (1.12 ± 0.06) × 10-2 to (5.79 ± 2.22) × 10-2 mL/g, respectively. The D e and K d values were shown to decrease with an increase in the bulk dry density of compacted bentonite. Our results show that HTO and 99Tc could be considered non-sorbent radionuclides. The data obtained in this study provide a valuable reference for the safety assessment of waste repositories.
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U2 - 10.1007/s41365-017-0221-z
DO - 10.1007/s41365-017-0221-z
M3 - Article
AN - SCOPUS:85016518159
SN - 1001-8042
VL - 28
JO - Nuclear Science and Techniques
JF - Nuclear Science and Techniques
IS - 5
M1 - 67
ER -