| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
|
| Presentation Title |
Irradiation Assisted Stress Corrosion Cracking of 304 and 316 Stainless Steels With Engineered IASCC-Resistant Microstructures |
| Author(s) |
Adam Eichhorn, Gokul Subramanian, Gary Was, Stephen Raiman |
| On-Site Speaker (Planned) |
Adam Eichhorn |
| Abstract Scope |
Irradiation Assisted Stress Corrosion Cracking has been observed since the 1960s when the earliest nuclear reactors developed cracks in their stainless steel cladding. Subsequent research has identified localized dislocation channeling as a key process behind IASCC. To potentially mitigate IASCC, novel steel microstructures that inhibit dislocation channels were irradiated and exposed to LWR conditions. Additively manufactured and hot isostatic-pressed 316 and oxide dispersion-strengthened 304L were compared to wrought 304L. Candidate materials were chosen for the microstructural stability of HIP steel during irradiation and the dislocation pinning by oxide particles of ODS steel. Four-point bend specimens were irradiated with 2 MeV protons at 360°C to a damage level of 5 dpa at a depth of 13 μm. Bend tests in simulated PWR primary water at 320 °C were performed to assess the IASCC susceptibility of each microstructure. Results of bend tests as they relate to the deformation microstructure will be presented. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Mechanical Properties, Nuclear Materials, Iron and Steel |