|About this Abstract
||2022 TMS Annual Meeting & Exhibition
||Environmentally Assisted Cracking: Theory and Practice
||Effect of Irradiation on the Cracking Behavior of Stainless Steels in Light Water Reactor Environment
||Yiren Chen, Bogdan Alexandreanu, Appajosula Rao
|On-Site Speaker (Planned)
The core internal components of light water reactors (LWRs) made of austenitic stainless steels are crucial for the safe and economic operation of nuclear power reactors. Subject to the harsh service environment inside the reactor core, a wide range of degradation processes can take place in reactor metals, leading to deteriorated service performance and reduced operational lifetime. To assure the long-term availability of LWRs, the extent of material degradation must be evaluated carefully. In this work, the cracking behavior of stainless steels was investigated with neutron-irradiated materials. Crack growth tests were performed in simulated LWR coolant, and the crack propagation rates of irradiated specimens were measured under cyclic and constant loads at different doses and stress intensity factors. The degree of irradiation embrittlement was also evaluated with J-R curve tests at several doses. The effect of irradiation on the cracking behavior of stainless steels in LWR environment was discussed.
||Iron and Steel, Nuclear Materials, Mechanical Properties