Measuring Key Parameters Governing Anion Transport Through Mx-80 Bentonite

The Nuclear Waste Management Organization (NWMO) is responsible for the design and implementation of Canada’s deep geological repository (DGR), which will be constructed ~ 500 m below ground surface to safely contain isolate used nuclear fuel. Used fuel containers (UFC), designed by NWMO as part multi-barrier system DGR, comprises an inner steel core with outer copper layer that serves a corrosion barrier. Surrounding UFC, highly compacted MX-80 bentonite (HCB) suppress transport corrosive agents UFC limit movement radionuclides out in unlikely event failure. Under anaerobic conditions, sulfate-reducing bacteria at interface host rock may produce bisulfide (HS−) can corrode Therefore, it crucial understand HS− mechanisms through assess long-term DGR performance. Due bentonite’s low permeability, diffusion-driven; therefore, apparent diffusion coefficient retardation are critical parameters performance assessment. This study aims quantify using experiments under range anticipated conditions (e.g., temperature, ionic concentration). paper outlines underpinning theory, experimental methodology developed conduct experiments, preliminary results. Altogether, this work bolsters confidence determine necessary key model reactive DGR’s