Radionuclide Transport through Cement Matrices

The disposal of low and intermediate level radioactive waste, particularly containing short-lived radionuclides, necessitates effective management strategies, and this study aims to explore the transport mechanisms of radionuclides through cement matrices. Utilizing experimental methodologies, diffusion and distribution coefficients for tritium (3H) and cesium-137 (137Cs) were measured in Portland cement matrices, which are crucial for the immobilization of waste generated at the Cernavoda Nuclear Power Plant. Given the high solubility of 137Cs and tritium, their release from cement waste matrices is understood to be diffusion-controlled. The results indicate that diffusion plays a significant role in the transport of radionuclides through low permeability environments, such as cement and clay materials. This insight is vital for informing the design of disposal facilities and enhancing the safety and efficiency of radioactive waste management practices over time. The findings contribute to the understanding of radionuclide behavior in cementitious materials, ensuring long-term containment and safety in nuclear waste disposal.