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Meeting Materials in Nuclear Energy Systems (MiNES) 2021
Symposium Materials in Nuclear Energy Systems (MiNES) 2021
Presentation Title Mechanical Behavior of Additively Manufactured 316L Stainless Steel and SiC before and after Neutron Irradiation
Author(s) Thak Sang Byun, Timothy G Lach, Maxim N Gussev, Annabelle G Le Coq, Xiang Chen, David A Collins, Gokul Vasudevamurthy, Kory D Linton, Kurt Terrani
On-Site Speaker (Planned) Thak Sang Byun
Abstract Scope The mechanical properties of additively manufactured (AM) 316L stainless steel (SS) and silicon carbide (SiC) were evaluated before and after irradiation in the High Flux Isotope Reactor to assess the in-reactor performance of AM components. For this research, 316L SS plates were manufactured using the laser powder bed fusion (LPBF) method and SiC disks by a combined process of binderjet 3D printing and chemical vapor infiltration (CVI). Baseline and post-irradiation tensile tests over a wide temperature range of room temperature–600 C were performed for the AM 316L alloy in different post-build heat-treatment conditions, and room temperature flexural strength testing for the SiC disk specimens in different printing orientations. This presentation is to summarize the outcome of these mechanical tests focusing on the irradiation-induced changes. We will also discuss about the statistical aspect of the strength data for both 316L and SiC materials and the size effect in SiC.
Proceedings Inclusion? Undecided

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