Effect of aging on failure mechanism of Alloy 709 at various temperatures
- North Carolina State Univ., Raleigh, NC (United States). Dept. of Mechanical and Aerospace Engineering. Advanced Materials Research Laboratory (AMRL)
- Univ. of Birmingham (United Kingdom). School of Metallurgy and Materials
Alloy 709 is a novel austenitic stainless steel with high temperature creep strength, weldability, and corrosion resistance. These properties make the material suitable for applications in the structure of next-generation nuclear power plants. Enduring high temperatures for an extended period of time in the harsh environments of a nuclear power plant results in thermal aging of the material. Therefore, it is imperative to study the effect of thermal aging on the microstructure and mechanical properties of Alloy 709 before its application in the next generation power plants. In this study, hot-processed (forged + rolled), annealed and quenched ingots of Alloy 709 are aged at 650 °C for 2000 h in air and then tested at various temperatures up to 850 °C in an in-situ heating-loading Scanning Electron Microscope (SEM) equipped with Energy Dispersive Spectroscopy (EDS) and Electron Backscatter Diffraction (EBSD). The effect of testing temperature and aging on microstructural evolutions during tensile testing of as-received and aged samples are studied. Furthermore, both as-received and aged samples displayed serrations and drop in ductility at elevated temperatures, due to the effect of dynamic strain aging (DSA). The occurrence of DSA activity was found within temperatures range of 500 °C–750 °C in as-received and 550 °C - 650 °C in aged samples. The aged samples showed less elongation accompanied by shallower dimples on the fractured surface, indicating less ductile failure mechanism compared to as-received samples. Failure mechanism observations on the fracture surface using SEM fractography are correlated to the observations made on the sample surface using in-situ SEM to achieve a complementary set of information to better understand the failure mechanism of this novel alloy.
- Research Organization:
- North Carolina State University, Raleigh, NC (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE); Research Council of the United Kingdom (RCUK)
- Grant/Contract Number:
- NE0008451; EP/N016351/1
- OSTI ID:
- 1850488
- Alternate ID(s):
- OSTI ID: 1778601
- Journal Information:
- Materials Characterization, Vol. 171, Issue C; ISSN 1044-5803
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- United States
- Language:
- English
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