Creep properties of advanced austenitic steel 709 determined through short experiments under in-situ neutron diffraction followed by TEM characterization
Journal Article
·
· Materials Characterization
- North Carolina State Univ., Raleigh, NC (United States)
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Here in this study, the creep mechanisms at play in Alloy 709 (Fe-20Cr-25Ni) are investigated by performing short-term creep-type tests under in-situ neutron diffraction experiments. Short tests are performed in the temperature range of 500 to 900 °C under constant load with a load ranging from 50 to 150 MPa. The creep exponent and activation energy are determined using the Bird-Mukherjee-Dorn relation and compared to that obtained from conventional longer creep tests from the literature. Scanning transmission electron microscopy (S/TEM) of the post-creep microstructure indicates that interaction of dislocations with precipitates are a dominant mechanism at play. Furthermore, local elemental mapping indicated chemical segregation at grain boundaries and formation of complex precipitates.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE; USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP); USDOE Office of Science (SC)
- Grant/Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1855652
- Alternate ID(s):
- OSTI ID: 1828798
- Journal Information:
- Materials Characterization, Journal Name: Materials Characterization Journal Issue: 2021 Vol. 182; ISSN 1044-5803
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Similar Records
Creep behavior of Alloy 709 at 700 °C
Characterization of Creep-Fatigue Crack Growth in Alloy 709 and Prediction of Service Lives in Nuclear Reactor Components (Final Report)
Shakedown Tests for Refurbished and Upgraded Frames and Initiation of Alloy 709 Creep Rupture Tests
Journal Article
·
Thu Jun 27 20:00:00 EDT 2019
· Materials Science and Engineering. A, Structural Materials: Properties, Microstructure and Processing
·
OSTI ID:1544774
Characterization of Creep-Fatigue Crack Growth in Alloy 709 and Prediction of Service Lives in Nuclear Reactor Components (Final Report)
Technical Report
·
Tue Apr 30 00:00:00 EDT 2019
·
OSTI ID:1511029
Shakedown Tests for Refurbished and Upgraded Frames and Initiation of Alloy 709 Creep Rupture Tests
Technical Report
·
Fri Sep 01 00:00:00 EDT 2017
·
OSTI ID:1394627