Effect of aging on failure mechanism of Alloy 709 at various temperatures
Creators
- 1. Advanced Materials Research Laboratory (AMRL), Department of Mechanical and Aerospace Engineering, North Carolina State University, Raleigh, NC 27606 (United States)
- 2. School of Metallurgy and Materials, University of Birmingham, Edgbaston, Birmingham B15 2TT (United Kingdom)
Description
Highlights: • in-situ SEM tests of as-received and aged Alloy 709 conducted at various temperatures; • serrations and ductility decline found between 500 and 750 °C due to DSA; • aging results in precipitation at grain boundaries, reduces percentage of solute atoms; • globular carbide precipitated at grain boundaries reduced plasticity; • as temperature increases the mechanism shifts from slip to grain boundary sliding. 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. 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.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.matchar.2020.110750Additional details
Identifiers
- DOI
- 10.1016/j.matchar.2020.110750;
- PII
- S104458032032221X;
Publishing Information
- Journal Title
- Materials Characterization
- Journal Volume
- 171
- Journal Page Range
- vp.
- ISSN
- 1044-5803
- CODEN
- MACHEX
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54039365
- Subject category
- S36: MATERIALS SCIENCE; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
- Descriptors DEI
- AUSTENITIC STEELS; CORROSION RESISTANCE; CREEP; DUCTILITY; ELECTRON DIFFRACTION; ELECTRONS; FRACTURES; GRAIN BOUNDARIES; NUCLEAR POWER PLANTS; PLASTICITY; PRECIPITATION; SCANNING ELECTRON MICROSCOPY; SPECTROSCOPY; STRAIN AGING; WELDABILITY
- Descriptors DEC
- AGING; ALLOYS; CARBON ADDITIONS; COHERENT SCATTERING; DIFFRACTION; ELECTRON MICROSCOPY; ELEMENTARY PARTICLES; FAILURES; FERMIONS; IRON ALLOYS; IRON BASE ALLOYS; LEPTONS; MECHANICAL PROPERTIES; MICROSCOPY; MICROSTRUCTURE; NUCLEAR FACILITIES; POWER PLANTS; SCATTERING; SEPARATION PROCESSES; STEELS; TENSILE PROPERTIES; THERMAL POWER PLANTS; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2020 Elsevier Inc. All rights reserved.