Interaction between spent fuel components and carbonate rocks

O Klein-BenDavid; Y Harlavan; I Levkov; N Teutsch; K G Brown; C Gruber; J Ganor

doi:10.1016/j.scitotenv.2019.06.396

Interaction between spent fuel components and carbonate rocks

Sci Total Environ. 2019 Nov 1:689:469-480. doi: 10.1016/j.scitotenv.2019.06.396. Epub 2019 Jun 26.

Authors

O Klein-BenDavid¹, Y Harlavan², I Levkov³, N Teutsch², K G Brown⁴, C Gruber⁴, J Ganor³

Affiliations

¹ Applied Chemistry Department, Nuclear Research Center - Negev, P.O. Box 9001, Be'er Sheva 8419001, Israel; Geological & Environmental Sciences Department, Ben-Gurion University of the Negev, Be'er Sheva 653 84105, Israel. Electronic address: ofrak1@gmail.com.
² Geological Survey of Israel, 32 Yeshayahu Leibowitz St., Jerusalem 9371234, Israel.
³ Geological & Environmental Sciences Department, Ben-Gurion University of the Negev, Be'er Sheva 653 84105, Israel.
⁴ The Department of Civil and Environmental Engineering, Vanderbilt University, Nashville, TN 37235, USA.

PMID: 31279194
DOI: 10.1016/j.scitotenv.2019.06.396

Abstract

Deep geological repository is considered the internationally accepted method for spent fuel (SF) disposal. In countries where salt, clay, tuff and granite are unavailable at geologically suitable area, other rock types may come into consideration. In Israel, carbonate rocks make up a significant portion of the surface and subsurface lithologies, thus, low permeability carbonates were evaluated as possible host rocks for a repository, and for an interim storage facility. Sorption and retardation capacity of SF components to low permeability carbonate rocks were evaluated using their chemical simulants. Strontium and Cs represent components that may leach during interim storage, while U and Ce (as a simulant for redox-active actinides) represent components that may leach under repository conditions. Rocks from the Upper Cretaceous Mount Scopus Group were sampled from boreholes at the Yamin Plateau, Israel. Single point batch experiments were conducted with synthetic rainwater spiked with tracers and interacted with five rock types of various particle sizes at 25 °C. Results were evaluated using the LeachXS™-ORCHESTRA geochemical speciation and data management program. Cerium removal was found to be related to the HCO₃^- concentration in solution, where Ce precipitated as Ce₂(CO₃)₃·XH₂O and as an amorphous carbonate phase. Removal of Cs and Sr was controlled by clays. No Sr co-precipitation as carbonate species was observed. Uranium was removed mainly by sorption onto solid organic matter, whereas clays had no significant role in U sorption. Iron-(hydr) oxides may have also played a role in U removal. Calculated partition coefficients for U, Cs, and Sr were in the order of 10¹-10² mL/g. Grain size had no significant effect on the retention capacity of the studied rocks due to similar effective surface area. The current study indicates that a repository or an interim storage facility within carbonate rocks, would provide only partial isolation of radionuclides from the environment, hence, additional engineered barriers may be required.

Keywords: Carbonate; Deep geological repository; Interim storage; Spent fuel.