Complexity of deformation mechanism in neutron-irradiated 304L austenitic stainless steel at microstructural scale

Nitish Bibhanshu, Maxim N. Gussev, Thomas M. Rosseel

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10 Scopus citations

Abstract

The deformation mechanisms of neutron-irradiated 304 L stainless steel have been investigated using the in-situ electron backscattered diffraction (EBSD) technique. To decipher the role of irradiation, a detailed analysis was performed on irradiated miniature samples and compared with nonirradiated samples. At three levels of engineering strain, —0.0%, 4.8%, and 14.5%—microstructural features as well as EBSD were recorded at the identical location during in-situ deformation testing. Post-mortem analysis of the EBSD data revealed that the neutron-irradiated samples had higher fractions of the slip bands even at low amounts of deformation. Along with the slip bands, the neutron-irradiated sample showed the twins and martensitic phase formed almost parallel to the slip bands. In addition, the image results also indicated that the formation of twins and phases associated with the slip bands. A detailed mechanistic understanding has been investigated to identify the (111)γ planes orientation with respect to the loading direction associated with the formation of twins and martensite. The newly formed deformation twins and martensite were also found to maintain this relationship when they existed together.

Original languageEnglish
Article number111218
JournalMaterials Characterization
Volume178
DOIs
StatePublished - Aug 2021

Funding

This manuscript has been authored in part by UT-Battelle LLC under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( http://energy.gov/downloads/doe-public-access-plan ). This research was supported by the U. S. Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability Program under contract DE-AC05-00OR22725 with UT-Battelle, LLC via Oak Ridge National Laboratory. The authors thank the French Alternative Energies and Atomic Energy Commission and ?lectricit? de France S.A. We would like to personally thank Dr. B. Tanguy (CEA) for providing archive material. Additionally, we would like to thank Dr. Wei Tang (Oak Ridge National Laboratory [ORNL]), Dr. T. S. Byun (ORNL), and Dr. Keyou Mao (ORNL) for reviewing the manuscript and providing valuable comments. Laurie Varma (ORNL) is gratefully acknowledged for document preparation. We also thank T. Dixon (ORNL) for help with specimen preparation for the in-situ experiment. This research was supported by the U. S. Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability Program under contract DE-AC05-00OR22725 with UT-Battelle, LLC via Oak Ridge National Laboratory. The authors thank the French Alternative Energies and Atomic Energy Commission and Électricité de France S.A. We would like to personally thank Dr. B. Tanguy (CEA) for providing archive material. Additionally, we would like to thank Dr. Wei Tang (Oak Ridge National Laboratory [ORNL]), Dr. T. S. Byun (ORNL), and Dr. Keyou Mao (ORNL) for reviewing the manuscript and providing valuable comments. Laurie Varma (ORNL) is gratefully acknowledged for document preparation. We also thank T. Dixon (ORNL) for help with specimen preparation for the in-situ experiment.

FundersFunder number
Office of Nuclear Energy, Light Water Reactor Sustainability ProgramDE-AC05-00OR22725
U.S. Department of Energy
Oak Ridge National Laboratory
UT-Battelle
Commissariat à l'Énergie Atomique et aux Énergies Alternatives

    Keywords

    • 304 L austenitic stainless steel
    • In-situ EBSD
    • Neutron irradiation

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