About this Abstract |
Meeting |
2022 TMS Annual Meeting & Exhibition
|
Symposium
|
Synergistic Irradiation, Corrosion, and Microstructural Evolution in Nuclear Materials
|
Presentation Title |
Effects of Water Radiolysis and Displacement Damage during Simultaneous Irradiation and Corrosion of 316L Stainless Steel |
Author(s) |
Rigel D. Hanbury, Jonas K. Heuer, Gary S. Was |
On-Site Speaker (Planned) |
Rigel D. Hanbury |
Abstract Scope |
Proton irradiation of 316L stainless steel discs was conducted during exposure in both water and steam environments for 24 h and 72 h with a damage rate of 7×10-7 dpa/s. To isolate radiolysis with minimal displacement damage, additional 316L sample surfaces oriented parallel to the transmitted proton beam were examined. To isolate displacement damage, a steam environment was used to minimize water radiolysis without changing the damage rate. Relative to a non-irradiated control, total oxidation was decreased by radiolysis and unaffected by displacement damage in 320 °C hydrogenated water. In 480 °C hydrogenated argon-steam, total oxidation was unaffected by radiolysis and increased with displacement damage relative to the non-irradiated control. The high level of water radiolysis by ion irradiation suppressed corrosion by increasing the electrochemical corrosion potential. In steam, where radiolysis was suppressed, displacement damage accelerated oxidation consistent with a transport-limited corrosion process. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Iron and Steel, Other |