Assessment of creep-fatigue behavior, deformation mechanisms, and microstructural evolution of alloy 709 under accelerated conditions
Source abstract
Abstract
Abstract Alloy 709 is a leading candidate structural material for sodium-cooled fast spectrum reactors (FSR), where creep-fatigue is a potential failure mode. Low cycle fatigue (LCF) and creep-fatigue tests with 30 min tensile hold times have been conducted to failure at 550 and 650 °C, corresponding to potential service and accelerated test temperatures, respectively. Creep-fatigue life is reduced relative to LCF at both temperatures, though significantly more at 550 °C compared to 650 °C. Differences in slip behavior, dynamic recovery, precipitate evolution, and strain-aging effects result in less stress relaxation and sustained high tensile stresses in creep-fatigue at 550 °C; thus, there is more intergranular damage compared to 650 °C.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: High Temperature Alloys and Creep · Nuclear Materials and Properties · Fatigue and fracture mechanics
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (36)
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