| Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water | |
| Deng, Ping1,2; Han, En-Hou1; Peng, Qunjia1,3; Sun, Chen4 | |
| Corresponding Author | Han, En-Hou(ehhan@imr.ac.cn) |
| 2020-08-18 | |
| Source Publication | ACTA METALLURGICA SINICA-ENGLISH LETTERS
 |
| ISSN | 1006-7191 |
| Pages | 13 |
| Abstract | Corrosion behavior and mechanism of irradiated 304 nuclear grade stainless steel were studied in simulated pressurized water reactor primary water. The microstructure of the oxide formed on the steel irradiated to different doses over an exposure period range of 25-1500 h was analyzed and compared. It was found that the general and intergranular corrosion rates of the steel were increased with irradiation dose, in correspondence with an evolution of the general oxide and the oxide formed at the grain boundary. Correlation of the oxide evolution with the corrosion kinetics and mechanism has been discussed in detail. |
| Keyword | Stainless steel Irradiation High-temperature corrosion Intergranular corrosion |
| Funding Organization | International Science & Technology Cooperation Program of China ; Essential Research Fund by SNPTC |
| DOI | 10.1007/s40195-020-01123-y |
| Indexed By | SCI |
| Language | 英语 |
| Funding Project | International Science & Technology Cooperation Program of China[2014DFA50800] ; Essential Research Fund by SNPTC[2015SN010-007] |
| WOS Research Area | Metallurgy & Metallurgical Engineering |
| WOS Subject | Metallurgy & Metallurgical Engineering |
| WOS ID | WOS:000560642400001 |
| Publisher | CHINESE ACAD SCIENCES, INST METAL RESEARCH |
| Citation statistics | |
| Document Type | 期刊论文 |
| Identifier | http://ir.imr.ac.cn/handle/321006/140358 |
| Collection | 中国科学院金属研究所 |
| Corresponding Author | Han, En-Hou |
| Affiliation | 1.Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China 2.Nucl Power Inst China, Chengdu 610213, Peoples R China 3.Suzhou Nucl Power Res Inst, Suzhou 215004, Peoples R China 4.State Power Investment Corp Res Inst, Beijing 102209, Peoples R China |
| Recommended Citation GB/T 7714 | Deng, Ping,Han, En-Hou,Peng, Qunjia,et al. Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water[J]. ACTA METALLURGICA SINICA-ENGLISH LETTERS,2020:13. |
| APA | Deng, Ping,Han, En-Hou,Peng, Qunjia,&Sun, Chen.(2020).Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water.ACTA METALLURGICA SINICA-ENGLISH LETTERS,13. |
| MLA | Deng, Ping,et al."Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water".ACTA METALLURGICA SINICA-ENGLISH LETTERS (2020):13. |
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