Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) (방사성폐기물학회지)

Korean Radioactive Waste Society (한국방사성폐기물학회)
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Sorption of Tc(IV) in Saline Solutions - I. Sorption on MX-80 and Granite in Ca-Na-Cl Solutions

  • Shinya Nagasaki (McMaster University) ;
  • Zhiwei Zheng (McMaster University) ;
  • Jianan Liu (McMaster University) ;
  • Jieci Yang (McMaster University) ;
  • Tammy (Tianxiao) Yang (Nuclear Waste Management Organization)
  • Received : 2024.04.26
  • Accepted : 2024.06.13
  • Published : 2024.09.30
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Abstract

Technetium-99 is identified as an element of interest for the safety assessment of a deep geological repository for used nuclear fuel. The sorption behavior of Tc(IV) onto MX-80 and granite in Ca-Na-Cl solutions of varying ionic strength (0.05-1 mol·kgw-1 (m)) and across a pHm range of 4-9 was studied in this paper. Sorption of Tc(IV) was found to be independent of ionic strength in the range of 0.05 to 1 m for both MX-80 and granite. Sorption of Tc(IV) on MX-80 increased with pHm from 4 to 7 and then decreased with pHm from 8 to 9. Sorption of Tc(IV) on granite gradually increased with pHm from 4 to 8 and then became almost constant or slightly decreased with pHm from 8 to 9. A 2 site protolysis non-electrostatic surface complexation and cation exchange sorption model successfully simulated sorption of Tc(IV) on MX-80 and granite. Optimized values of surface complexation constants (log K0) are proposed.

Keywords

Acknowledgement

This work was funded by the Nuclear Waste Management Organization of Canada. The authors appreciate Prof. Koichiro Takao at the Tokyo Institute of Technology and Dr. Taishi Kobayashi at Kyoto University for their valuable comments on the experimental methods and the procedure for confirmation of the reduction of Tc(VII) to Tc(IV).

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