| Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor | |
| Deng, Ping1,2; Peng, Qunjia1,3; Han, En-Hou2 | |
| Corresponding Author | Peng, Qunjia(pengqunjia@yahoo.com) |
| 2021-01-14 | |
| Source Publication | SCIENTIFIC REPORTS
 |
| ISSN | 2045-2322 |
| Volume | 11Issue:1Pages:9 |
| Abstract | 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. |
| Funding Organization | International Science & Technology Cooperation Program of China |
| DOI | 10.1038/s41598-020-80600-x |
| Indexed By | SCI |
| Language | 英语 |
| Funding Project | International Science & Technology Cooperation Program of China[2014DFA50800] |
| WOS Research Area | Science & Technology - Other Topics |
| WOS Subject | Multidisciplinary Sciences |
| WOS ID | WOS:000626774100085 |
| Publisher | NATURE RESEARCH |
| Citation statistics | |
| Document Type | 期刊论文 |
| Identifier | http://ir.imr.ac.cn/handle/321006/161070 |
| Collection | 中国科学院金属研究所 |
| Corresponding Author | Peng, Qunjia |
| Affiliation | 1.Nucl Power Inst China, Chengdu 610213, Peoples R China 2.Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China 3.Suzhou Nucl Power Res Inst, Suzhou 215004, Peoples R China |
| Recommended Citation GB/T 7714 | Deng, Ping,Peng, Qunjia,Han, En-Hou. Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor[J]. SCIENTIFIC REPORTS,2021,11(1):9. |
| APA | Deng, Ping,Peng, Qunjia,&Han, En-Hou.(2021).Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor.SCIENTIFIC REPORTS,11(1),9. |
| MLA | Deng, Ping,et al."Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor".SCIENTIFIC REPORTS 11.1(2021):9. |
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