The radiation dose within a Pressurized Water Reactor (PWR) is a critical factor influencing the operational safety of nuclear power plants. The operational lifecycle of the reactor leads to the activation of corrosion products due to radiation exposure, which ultimately accumulate on the surfaces of the reactor system piping. This research aims to develop a kinetic model based on mixed potential theory, enabling the quantification of release rates of soluble corrosion products for various elemental compositions within the piping material. The primary computational procedure begins with the iterative determination of the corrosion potential to identify the corrosion current density. Subsequently, the oxide film calculation module, tailored to the selected structural material, computes the thickness and composition of the oxide film. A mass transfer model is then employed to quantify both direct diffusion and oxide film dissolution, thus determining the total quantity of corrosion products entering the coolant. Utilizing the research model, commonly used alloy materials are selected as piping materials to investigate the effects of different environmental parameters on the release rates of iron (Fe), chromium (Cr), and nickel (Ni). The corrosion release rates of soluble corrosion products, including Fe, Cr, and Ni, were calculated under various conditions, and the curve chart of the trend is drawn.