Chimi, Yasuhiro; Kasahara, Shigeki; Seto, Hitoshi*; Kitsunai, Yuji*; Koshiishi, Masato*; Nishiyama, Yutaka 
In order to understand irradiation-assisted stress corrosion cracking (IASCC) growth behavior, crack growth rate (CGR) tests have been performed in simulated Boiling Water Reactor water conditions at 
288
C on neutron-irradiated 316L stainless steels (SSs) at 12-14 dpa. After the tests, the microstructures near the crack tip of the specimens are examined with scanning transmission electron microscope (FE-STEM). In comparison with a previous study at 
2 dpa, this result shows a less benefit of low electrochemical corrosion potential (ECP) conditions on CGR. A crack tip immersed over 1000 hours was filled with oxides, while almost no oxide film was observed near the crack front in the low-ECP conditions. In addition, a high density of deformation twins and dislocations were found near the fracture surface of the crack front. It is considered that both localized deformation and oxidation are possible dominant factors for the SCC growth in highly irradiated SSs.
Language |
: | English |
|---|---|---|
Journal |
: | |
Volume |
: | |
Number |
: | |
Pages |
: | p.1039 - 1054 |
Publication Year/Month |
: | 2018/00 |
Meeting title |
: | |
Held date |
: | 2017/08 |
Location (city) |
: | Portland |
Location (country) |
: | U.S.A. |
Paper URL |
: |
|
Keywords |
: | IASCC; Crack Growth Rate; Microstructure; Localized Deformation; Oxide Film; Austenitic Stainless Steel; Neutron Irradiation; BWR |
Cooperating Institute |
: |
Accesses |
: |
- Accesses |
|---|---|---|
InCites™ |
: |
Percentile:58 Category:Materials Science, Multidisciplinary |
Altmetrics |
: |
[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.
