Abstract
Gen-IV nuclear reactors require materials to operate under much harsher conditions necessitating the development of advanced structural materials. Sodium-cooled Fast Reactor (SFR) is a Gen-IV nuclear reactor with a high level of technology readiness. Alloy 709, Fe-25Ni-20Cr (wt%) alloyed with Nb and stabilized with nitrogen, is an advanced austenitic stainless steel having promising set of properties for SFRs. However, the creep-fatigue deformation behavior is unknown for this alloy. This work focuses on evaluating creep-fatigue interaction in this alloy. We report here a creep-fatigue study conducted at 750 °C using triangular waveform following the ASTM standard E2714–13 at 0.1 Hz frequency. The creep-fatigue tests were conducted in strain-controlled mode where strain amplitudes of 0.2% and 0.5% were used. The microstructural examination in as-received and post-deformation conditions were carried out using scanning and transmission electron microscopes. The creep-fatigue lives at 0.2% and 0.5% strain amplitudes were 17,416 and 526 cycles, respectively. The comparison of the TEM micrographs between as-received and creep-fatigue deformed at 0.5% strain amplitude showed higher dislocation density and loosely defined subgrains in the deformed alloy. The fractographs indicated that for the samples deformed at 0.2% strain amplitude, fatigue might have been the dominant mode of deformation whereas for the sample deformed at 0.5% strain amplitude, fatigue and creep both might have contributed to the overall deformation of the alloy.
This is a preview of subscription content, log in via an institution.
Buying options
Tax calculation will be finalised at checkout
Purchases are for personal use only
Learn about institutional subscriptionsReferences
Zinkle, S.J., Busby, J.T.: Structural materials for fission & fusion energy. Mater. Today. 12, 12–19 (2009)
Zinkle, S.J., Was, G.S.: Materials challenges in nuclear energy. Acta Mater. 61, 735–758 (2013)
Allen, T., Balbaud-Celerier, F., Asayama, T., Pouchon, M., Busby, J., Maloy, S., Park, J., Fazio, C., Dai, Y., Agostini, P.: Status Report on Structural Materials for Advanced Nuclear Systems. Organization for Economic Co-Operation and Development, France, NEA – 6409 (2013)
Dieter, G.E.: Mechanical Metallurgy, 3rd edn. McGraw-Hill, New York (1986)
Rodriguez, P., Rao, K.B.S.: Nucleation and growth of cracks and cavities under creep-fatigue interaction. Prog. Mater. Sci. 37, 403–480 (1993)
Yagi, K., Kanemaru, O., Kubo, K., Tanaka, C.: Life prediction of 316 stainless steel under creep-fatigue loading. Fatigue Fract. Eng. Mater. Struct. 9, 395–408 (1987)
Acknowledgements
The authors would like to acknowledge the financial support through award DOE/NEUP project #15-8582 for this work. The authors would also like to acknowledge the use of microscopy facility at Advanced Instrumentation Facility at North Carolina State University Raleigh USA.
Author information
Authors and Affiliations
Editor information
Editors and Affiliations
Rights and permissions
Copyright information
© 2019 The Society for Experimental Mechanics, Inc.
About this paper
Cite this paper
Kumar, N., Alomari, A., Murty, K.L. (2019). Understanding Creep-Fatigue Interaction in Fe-25Ni-20Cr (wt%) Austenitic Stainless Steel. In: Arzoumanidis, A., Silberstein, M., Amirkhizi, A. (eds) Challenges in Mechanics of Time-Dependent Materials, Volume 2. Conference Proceedings of the Society for Experimental Mechanics Series. Springer, Cham. https://doi.org/10.1007/978-3-319-95053-2_5
Download citation
DOI: https://doi.org/10.1007/978-3-319-95053-2_5
Published:
Publisher Name: Springer, Cham
Print ISBN: 978-3-319-95052-5
Online ISBN: 978-3-319-95053-2
eBook Packages: EngineeringEngineering (R0)