Abstract
Intergranular stress corrosion cracking (IGSCC) on stainless steel and nickel-base alloy components has been a major material degradation issue for decades for all light water reactors (LWRs) around the world. To ensure operation safety, an optimization on the coolant chemistry in the primary coolant circuit of a nuclear reactor is essential no matter what type or generation the reactor belongs to. In light of the safety demand and the lack of essential water chemistry information in a LWR, the only feasible approach to accomplish the foregoing task of understanding water chemistry state is to conduct a series of theoretical analyses. In this study, a radiolysis model was therefore developed for analyzing the concentrations of electro active radiolysis products in the coolant. The simulation would produce predicted results pertinent to the water chemistry variation and the corrosion behavior of structure materials in the primary coolant system of a LWR.