TEM Specimen Manufacturing to Support Analysis of IASCC Mechanisms in Irradiated Austenitic Steels – Light-Water– Relevant Materials

The present report describes the manufacturing of samples for advanced microstructure studies of mechanisms of irradiation-assisted stress corrosion cracking (IASCC) in the materials of light-water reactor (LWR) internal components. The samples were manufactured via FIB (focused ion beam milling) from 4-point-bend specimens subjected to oxidation and mechanical loading in a simulated LWR environment (primary water, PW). The corrosion tests were conducted at the University of Michigan (UM), and the tested specimens were transported to ORNL to perform FIB work. Finally, the manufactured FIB specimens were shipped back to the UM for microstructure characterization. Section 1 in the report provides a brief introduction; Section 2 describes materials, their in-service and irradiation history, and the geometry of specimens for IASCC testing. Section 3 documents typical work steps (specimen mapping) and reports the number of manufactured FIB objects. Section 4 briefly describes the preliminary results of microstructure analysis performed at the University of Michigan and highlights the key findings. The summary and conclusions section discusses future possible future steps and generalizes the obtained results, their unique character, and their importance for the nuclear industry.. Authors: Gussev, Maxim N. [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000168140737); Mattingly, Gavin E. [Oak Ridge Associated Universities (ORAU), Oak Ridge, TN (United States)]; Sun, Kai [Univ. of Michigan, Ann Arbor, MI (United States)]; Was, Gary [Univ. of Michigan, Ann Arbor, MI (United States)]; Linton, Kory [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)] (ORCID:0000000230024623). DOE Contract: AC05-00OR22725. Subjects: 22 GENERAL STUDIES OF NUCLEAR REACTORS; 36 MATERIALS SCIENCE