EFFECT OF CARBON CONTENT ON THE IASCC SUSCEPTIBILITY OF AISI 304 SS IN BWR CONDITIONS

摘要

Intergranular stress corrosion cracking (IGSCC) affects sensitized stainless steels (SS) at high temperature, like operating conditions of nuclear power plants, when they are exposed to tensile stress and an oxygenated environment. Non-sensitized materials can becomes susceptible to SCC when they are exposed to neutron irradiation due to Irradiation Assisted Stress Corrosion Cracking (IASCC). This paper presents Slow Strain Rate Tests (SSRT) of AISI 304 SS irradiated with two different carbon contents, under simulating nuclear power plant operating conditions. The objectives were to study the effect of carbon content in the IASCC susceptibility and the synergistic effect between neutron irradiation and thermal sensitization. Results of this work indicated that neutron irradiation enhances susceptibility of sensitized material. Furthermore, low carbon material becomes susceptible to IASCC only at highly oxidant environments.