Modeling the corrosion behaviors of the heat transport circuits of light water nuclear reactors

To model the corrosion behaviors of the heat transport circuits of light water reactors, a mixed potential model (MPM) has been developed and applied to both boiling water reactors (BWRS) and pressurized water reactors (PWRs). Using the data generated by the GE/UKEA-Harwell radiolysis model, electrochemical potentials (ECPs) have been calculated for the heat transport circuits of eight BWRs operating under hydrogen water chemistry (HWC). By modeling the corrosion behaviors of these reactors, the effectiveness of HWC at limiting IGSCC and IASCC can be determined. For simulating PWR primary circuits, a chemical-radiolysis model (developed by the authors) was used to generate input parameters for the NWM. Corrosion potentials of Type 304 and 316 SSs in PWR primary environments were calculated using the NWM and were found to be in good agreement with the corrosion potentials measured in the laboratory for simulated PWR primary environments