|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Accelerated Materials Evaluation for Nuclear Application Utilizing Test Reactors, Ion Beam Facilities and Integrated Modeling
||Self-ion Irradiation Induced Dispersoid Instabilities and Dispersiod-defect Interactions in ODS Alloys
||Tianyi Chen, Jonathan G. Gigax, Hyosim Kim, Chao-Chen Wei, Di Chen, Frank A. Garner, Lin Shao
|On-Site Speaker (Planned)
Oxide-dispersion-strengthened (ODS) ferritic-martensitic steels are candidate materials for various advanced concept reactors. Dispersoid stability and dispersoid-defect interactions under irradiation conditions are thought very critical to maintenance of sustained radiation tolerance of ODS alloys, especially at higher temperatures. Using self-ion irradiation we examined, at high dpa levels, diverse ODS alloys, i.e. MA 956, 12Cr dual-phase ODS, etc. Dispersoids in different alloys behave significantly different. For example, MA956 at 450C was observed to exhibit a defect-collecting phenomenon, where voids were found almost always attached to dispersoids. The strong correlation of densities and sizes of voids and dispersoids suggest that voids and dispersoids co-evolved as single coordinated units. On the other hand, dispersoids in 12Cr dual-phase ODS at 475C appear to suppress void formation in both phases with no voids attached to dispersoids. While dispersoid size was initially different in the two phases the equilibrium size under irradiation converged to the same value.
||Planned: A print-only volume