|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Environmentally Assisted Cracking: Theory and Practice
||Cracking Behavior and Fracture Toughness of Irradiated Austenitic Stainless Steels in LWR Environments
||Yiren Chen, Bogdan Alexandeanu, Ken Natesan, Yong Yang, Appajosula Rao
|On-Site Speaker (Planned)
The service performance of austenitic stainless steels subjected to reactor core environments is critical for the safe and economic operation of light water reactors (LWRs). Exposed to high levels of neutron irradiation, the core internal materials undergo significant microstructural changes and property degradation during power operations. Of particular concern are the deteriorated fracture resistance and elevated cracking susceptibility. Premature failures resulting from irradiation-assisted stress corrosion cracking (IASCC) have been observed for reactor internal components and have become a critical issue for the service lifetime extension of aging LWRs. This talk will present experimental data on crack growth rates and fracture toughness of neutron-irradiated stainless steels and welds, and discuss the effects of corrosion potential and irradiation embrittlement on stress corrosion cracking of irradiated materials in the context of IASCC mechanisms.
||Planned: Supplemental Proceedings volume