Jornal de Estudos de Defesa e Gestão de Recursos

PWSCC mitigation for life management

It became very clear, due to the safety of the plant the importance of study occurrence reactor coolant system (RCS) issues especially the primary water stress corrosion cracking (PWSCC). PWSCC refers to cracks found in the Piping System of Reactor Cooling System and it occurs when three controlling factors, material susceptibility, tensile stress, and the environment, are sufficiently severe. PWSCC of Alloy 600 nickel-chromium-iron base metal and related Alloys 82 and 182 weld metal has become an increasing concern for commercial Pressurized Water Reactor (PWR) plants. Cracks and leaks have been discovered in Alloy 600/82/182 materials at numerous PWR plant primary coolant system locations. Basic management strategies to minimize the occurrence of damage to RCS piping consist of proper operation guidelines, inspection and monitoring or maintenance, and an assessment of degradation. In this paper, PWSCC overview and controlling methodology are introduced also the 3D model of RCS created and internal inspection path for RCS piping are introduced based on the 3D model of RCS.