| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Components
|
| Presentation Title |
Stress Corrosion Cracking Resistance of FeCrAl Alloys in Light Water Reactor Environments |
| Author(s) |
Raul B. Rebak, Liang Yin, Andrew Hoffman |
| On-Site Speaker (Planned) |
Raul B. Rebak |
| Abstract Scope |
In the last decade extensive research has been conducted worldwide to determine the suitability of iron-chrome-aluminum (FeCrAl) alloys as ATF cladding of uranium dioxide nuclear fuel in light waterpower reactors. Since FeCrAl alloys have not been used in nuclear reactors, it is important to characterize their behavior in the entire fuel cycle. Stress corrosion cracking (SCC) studies were conducted for two FeCrAl alloys (APMT and C26M) using compact tension specimens in typical simulated boiling water reactor conditions at 288°C and containing either dissolved hydrogen or oxygen. Crack propagation studies showed that both ferritic FeCrAl alloys were highly resistant to SCC at stress intensities below 40 MPa√m. The current work confirms that ferritic stainless alloys are orders of magnitude more resistant to SCC than austenitic type of materials such as type 304/316 stainless steels. |
| Proceedings Inclusion? |
Planned: |