TY - GEN
T1 - Localized Deformation Investigation in Irradiated Materials via Electron Microscopy, EBSD, and In-Situ Mechanical Testing
AU - Gussev, Maxim N
AU - Leonard, Keith
PY - 2018
Y1 - 2018
N2 - This report describes the preliminary results of an analysis of dislocation defect structures in nondeformed and deformed austenitic stainless steels – materials of light water reactor internal components. The analysis was performed using an advanced modern approach: high-resolution electron backscatter diffraction (HR-EBSD). Work was performed at Oak Ridge National Laboratory’s Low Activation Materials Development and Analysis (LAMDA) facility. The report is divided into sections describing specific aspects of the project. Section 1 describes the necessity and importance of the defect microstructure analysis and demonstrates that there are very limited data regarding dislocation and defect population at the meso-level (i.e., a grain or group of interacting grains). Section 1 also introduces the HR-EBSD approach used in this research and provides a limited background. Section 2 describes the scanning electron microscope/EBSD systems available at the LAMDA facility, materials investigated in the present work, and hardware and software requirements for the HR-EBSD analysis. Section 3 provides preliminary HR-EBSD results for nonirradiated austenitic stainless steel in contrast to and in comparison with the conventional EBSD outcome. Section 4 describes the HR-EBSD results for austenitic stainless steel irradiated in a commercial-type nuclear power plant and subjected to in-situ mechanical testing. The analysis is focused on mapping and analyzing the geometrically necessary dislocations before and after deformation at small strain levels. As expected, the results will be beneficial for performing corrosion tests, including electrochemical microscopy, which is currently being performed within the Light Water Reactor Sustainability program at the University of California–Los Angeles (Dr. G. Sant). Section 5 summarizes the work performed, presents conclusions, and discusses future activities for this research.
AB - This report describes the preliminary results of an analysis of dislocation defect structures in nondeformed and deformed austenitic stainless steels – materials of light water reactor internal components. The analysis was performed using an advanced modern approach: high-resolution electron backscatter diffraction (HR-EBSD). Work was performed at Oak Ridge National Laboratory’s Low Activation Materials Development and Analysis (LAMDA) facility. The report is divided into sections describing specific aspects of the project. Section 1 describes the necessity and importance of the defect microstructure analysis and demonstrates that there are very limited data regarding dislocation and defect population at the meso-level (i.e., a grain or group of interacting grains). Section 1 also introduces the HR-EBSD approach used in this research and provides a limited background. Section 2 describes the scanning electron microscope/EBSD systems available at the LAMDA facility, materials investigated in the present work, and hardware and software requirements for the HR-EBSD analysis. Section 3 provides preliminary HR-EBSD results for nonirradiated austenitic stainless steel in contrast to and in comparison with the conventional EBSD outcome. Section 4 describes the HR-EBSD results for austenitic stainless steel irradiated in a commercial-type nuclear power plant and subjected to in-situ mechanical testing. The analysis is focused on mapping and analyzing the geometrically necessary dislocations before and after deformation at small strain levels. As expected, the results will be beneficial for performing corrosion tests, including electrochemical microscopy, which is currently being performed within the Light Water Reactor Sustainability program at the University of California–Los Angeles (Dr. G. Sant). Section 5 summarizes the work performed, presents conclusions, and discusses future activities for this research.
U2 - 10.2172/3002977
DO - 10.2172/3002977
M3 - Technical Report
CY - United States
ER -