About this Abstract |
| Meeting |
2020 TMS Annual Meeting & Exhibition
|
| Symposium
|
Environmental Degradation of Additively Manufactured Alloys
|
| Presentation Title |
SCC and IASCC of Printed 316L for Use in the Nuclear Industry |
| Author(s) |
Michael Mcmurtrey, Xiaoyuan Lou, Gary Was |
| On-Site Speaker (Planned) |
Michael Mcmurtrey |
| Abstract Scope |
Additive manufacturing (AM) is an area of interest to the nuclear industry for its benefits over traditional manufacturing, such as the ability to create complex geometries without welds. However, the behavior/properties of AM metals are poorly understood, especially with respect to irradiation effects. For stainless steel nuclear components, irradiation assisted stress corrosion cracking (IASCC) is particularly important. This work examines the IASCC behavior of proton irradiated AM 316L steel (direct energy deposition and powder bed AM specimens) and wrought 316L steel strained in simulated BWR NWC water (288°C, 0.2 µS/cm). TEM, SEM, confocal microscopy and X-ray microCT were used to examine the specimens. This work found that the wrought 316L was more susceptible to IASCC than the AM steel, however, significant IASCC was observed in the AM steel when tested with the tensile axis parallel to the build direction. HIPing was found to improve the IASCC resistance of AM steel. |
| Proceedings Inclusion? |
Planned: Supplemental Proceedings volume |