Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water
文献类型：期刊论文
| 作者 | Deng, Ping1,3; Han, En-Hou3; Peng, Qunjia3,4; Sun, Chen2 |
| 刊名 | ACTA METALLURGICA SINICA-ENGLISH LETTERS
 |
| 出版日期 | 2020-08-18 |
| 页码 | 13 |
| 关键词 | Stainless steel Irradiation High-temperature corrosion Intergranular corrosion |
| ISSN号 | 1006-7191 |
| DOI | 10.1007/s40195-020-01123-y |
| 通讯作者 | Han, En-Hou(ehhan@imr.ac.cn) |
| 英文摘要 | 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. |
| 资助项目 | International Science & Technology Cooperation Program of China[2014DFA50800] ; Essential Research Fund by SNPTC[2015SN010-007] |
| WOS研究方向 | Metallurgy & Metallurgical Engineering |
| 语种 | 英语 |
| WOS记录号 | WOS:000560642400001 |
| 出版者 | CHINESE ACAD SCIENCES, INST METAL RESEARCH |
| 资助机构 | International Science & Technology Cooperation Program of China ; Essential Research Fund by SNPTC |
| 源URL | [http://ir.imr.ac.cn/handle/321006/140357]  |
| 专题 | 金属研究所_中国科学院金属研究所 |
| 通讯作者 | Han, En-Hou |
| 作者单位 | 1.Nucl Power Inst China, Chengdu 610213, Peoples R China 2.State Power Investment Corp Res Inst, Beijing 102209, Peoples R China 3.Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China 4.Suzhou Nucl Power Res Inst, Suzhou 215004, Peoples R China |
| 推荐引用方式 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. |
入库方式： OAI收割
来源：金属研究所
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