Abstract
In order to understand irradiation-assisted stress corrosion cracking (IASCC) growth behavior, crack growth rates (CGRs), locally deformed microstructure, and oxide film properties for neutron-irradiated austenitic stainless steels (SSs) are investigated. Crack growth rate tests have been performed in simulated Boiling Water Reactor (BWR) water conditions (at ~288 ℃) on a neutron-irradiated 316L SS at ~12–14 dpa. After the crack growth rate tests, the microstructures near the crack tip of the CT specimens are examined with scanning transmission electron microscope (FE-STEM). In comparison with a previous study at
Author supplied keywords
Cite
CITATION STYLE
Chimi, Y., Kasahara, S., Seto, H., Kitsunai, Y., Koshiishi, M., & Nishiyama, Y. (2019). Evaluation of crack growth rates and microstructures near the crack tip of neutron-irradiated austenitic stainless steels in simulated bwr environment. In Minerals, Metals and Materials Series (pp. 2255–2270). Springer International Publishing. https://doi.org/10.1007/978-3-030-04639-2_152
Register to see more suggestions
Mendeley helps you to discover research relevant for your work.
