|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Accelerated Materials Evaluation for Nuclear Application Utilizing Test Reactors, Ion Beam Facilities and Integrated Modeling
||TEM Characterization of Neutron-irradiated Cast Austenitic Stainless Steel at 320°C to 0.08 dpa
||Wei-Ying Chen, Yiren Chen, Xuan Zhang, Chi Xu, Mark Kirk, Meimei Li
|On-Site Speaker (Planned)
Cast austenitic stainless steels (CASS) are used for components with complex shapes in the cooling system of light water reactors. Due to both thermal aging and irradiation embrittlement, the long-term performance of CASS materials is of concern. Previous fracture toughness J-R curve tests showed a reduction in fracture resistance in both as-received and thermally aged (400°C for 10,000 hours) CASS materials after a neutron irradiation of ~0.08 dpa at ~320°C. To understand the embrittlement mechanism, unaged and aged CASS specimens were characterized with TEM before and after the irradiation. Irradiation-enhanced precipitation and coarsening of G-phase in the ferritic phase were observed. The average precipitate size and density were 5.1 nm and 2.2×1022 1/m3, respectively, for the neutron-irradiated specimen as compared to 3.2 nm and 4.9×1021 1/m3 for the thermally-aged specimen. A few dislocation loops were observed in the irradiated specimens with distinct morphologies between the ferritic and austenitic phases.
||Planned: A print-only volume