About this Abstract |
Meeting |
MS&T22: Materials Science & Technology
|
Symposium
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Tackling Structural Materials Challenges for Advanced Nuclear Reactors
|
Presentation Title |
Mechanical Behavior of Additively Manufactured Steels with Monotonic and Graded Microstructures |
Author(s) |
Thak Sang Byun, Maxim G Gussev, Timothy G Lach |
On-Site Speaker (Planned) |
Thak Sang Byun |
Abstract Scope |
Mechanical behaviors of additively manufactured (AM) single-phase austenitic stainless steel (316L) and compositionally (microstructurally) graded alloy (CGA) were investigated in various conditions using in-situ SEM, ex-situ tensile testing and TEM. Uniaxial tensile testing before and after irradiation was performed for AM 316L to assess its performance as a reactor core structural material. The AM 316L stainless steel, regardless of post-build treatment, showed higher strength and comparable ductility compared to the wrought 316L stainless steel. It also demonstrated high resistance to the neutron irradiation at 300 and 600°C. For the CGA build, the electron back scattered diffraction (EBSD) maps display a clear microstructural transition from an austenite dominant structure, to a complex composite structure containing ferrite, martensite, and austenite, and then to a fully ferritic structure. Deformation mechanism was highly dependent on the local composition. In particular, the Ni/Mn-rich austenite showed a complex deformation-induced martensitic transformation involving epsilon martensite. |