About this Abstract |
Meeting |
2024 TMS Annual Meeting & Exhibition
|
Symposium
|
Environmentally Assisted Cracking: Theory and Practice
|
Presentation Title |
Precursor Damage Evolution and Stress Corrosion Crack Initiation of Ni-base Alloy 600 and Alloy 690 in PWR Primary Water |
Author(s) |
Ziqing Zhai, Mychailo Toloczko, Karen Kruska, Stephen Bruemmer, Jia Liu |
On-Site Speaker (Planned) |
Ziqing Zhai |
Abstract Scope |
Understanding stress corrosion crack (SCC) initiation of the first (Alloy 600) and second (Alloy 690) generation Ni-base alloys is of critical importance to material degradation prediction and plant life management of existing pressurized water reactors (PWRs). This presentation summarizes the multi-year SCC initiation research at Pacific Northwest National Laboratory on both Alloy 600 and Alloy 690 in simulated PWR primary water. State-of-the-art SCC initiation testing was performed on multiple Alloy 600 and Alloy 690 heats to collect crack initiation time using an in-situ monitoring technique, and advanced microscopy tools were used to characterize precursors and cracks at nm-to-mm scale. The coupled high-precision testing and systematic microscopy offered new insights into crack initiation mechanisms and the effect of various material, environmental, and mechanical factors. This presentation will highlight the different behavior in crack initiation in Alloy 600 and Alloy 690 and the role of key influencing factors during the initiation process. |
Proceedings Inclusion? |
Planned: |
Keywords |
Mechanical Properties, Environmental Effects, Characterization |