Journal
SCIENTIFIC REPORTS
Volume 11, Issue 1, Pages -Publisher
NATURE RESEARCH
DOI: 10.1038/s41598-020-80600-x
Keywords
-
Categories
Funding
- International Science & Technology Cooperation Program of China [2014DFA50800]
Ask authors/readers for more resources
The study investigated grain boundary oxidation of proton-irradiated 304 nuclear grade stainless steel in primary water of pressurized water reactor by studying the microstructure of the oxide and oxide precursor on an atom-by-atom basis. The results showed that increasing irradiation dose promoted grain boundary oxidation, leading to the formation of different oxide and oxide precursor. The correlation of oxide and oxide precursor with the grain boundary oxidation behavior was discussed in detail.
Grain boundary (GB) oxidation of proton-irradiated 304 nuclear grade stainless steel in primary water of pressurized water reactor was investigated. The investigation was conducted by studying microstructure of the oxide and oxide precursor formed at GB on an atom-by-atom basis by a combination of atom-probe tomography and transmission electron microscope. The results revealed that increasing irradiation dose promoted the GB oxidation, in correspondence with a different oxide and oxide precursor formed at the GB. Correlation of the oxide and oxide precursor with the GB oxidation behavior has been discussed in detail.
Authors
I am an author on this paper
Click your name to claim this paper and add it to your profile.
Reviews
Recommended
No Data Available
Share Paper
