| Effect of irradiation on corrosion of 304 nuclear grade stainless steel in simulated PWR primary water | |
| Deng, Ping; Peng, Qunjia; Han, En-Hou; Ke, Wei; Sun, Chen; Jiao, Zhijie; Peng, QJ (reprint author), Chinese Acad Sci, Key Lab Nucl Mat & Safety Assessment, Inst Met Res, Shenyang 110016, Liaoning, Peoples R China. | |
| 2017-10-01 | |
| Source Publication | PERGAMON-ELSEVIER SCIENCE LTD
 |
| ISSN | 0010-938X |
| Volume | 127Pages:91-100 |
| Abstract | Effect of irradiation on corrosion of 304 nuclear grade stainless steel (304NG SS) in simulated primary water of pressurized water reactor was investigated. The investigation was conducted by comparing the microstructure of the oxide scale formed on the steel irradiated to different doses by proton. The results revealed that increasing irradiation dose promoted both the corrosion and intergranular corrosion of 304NG SS. This is attributed to the irradiation induced defects as well as the Cr depletion at the grain boundary in the steel.; Effect of irradiation on corrosion of 304 nuclear grade stainless steel (304NG SS) in simulated primary water of pressurized water reactor was investigated. The investigation was conducted by comparing the microstructure of the oxide scale formed on the steel irradiated to different doses by proton. The results revealed that increasing irradiation dose promoted both the corrosion and intergranular corrosion of 304NG SS. This is attributed to the irradiation induced defects as well as the Cr depletion at the grain boundary in the steel. |
| description.department | [deng, ping ; peng, qunjia ; han, en-hou ; ke, wei] chinese acad sci, key lab nucl mat & safety assessment, inst met res, shenyang 110016, liaoning, peoples r china ; [deng, ping] univ sci & technol china, sch mat sci & engn, shenyang 110016, liaoning, peoples r china ; [peng, qunjia ; sun, chen] state power investment corp res inst, beijing 102209, peoples r china ; [jiao, zhijie] univ michigan, dept nucl engn & radiol sci, ann arbor, mi 48109 usa |
| Keyword | Stainless Steel Tem High Temperature Corrosion Intergranular Corrosion |
| Subject Area | Materials Science, Multidisciplinary ; Metallurgy & Metallurgical Engineering |
| Funding Organization | International Science & Technology Cooperation Program of China [2014DFA50800]; National Natural Science Foundation of China [51571204] |
| Indexed By | SCI |
| Language | 英语 |
| Document Type | 期刊论文 |
| Identifier | http://ir.imr.ac.cn/handle/321006/79062 |
| Collection | 中国科学院金属研究所 |
| Corresponding Author | Peng, QJ (reprint author), Chinese Acad Sci, Key Lab Nucl Mat & Safety Assessment, Inst Met Res, Shenyang 110016, Liaoning, Peoples R China. |
| Recommended Citation GB/T 7714 | Deng, Ping,Peng, Qunjia,Han, En-Hou,et al. Effect of irradiation on corrosion of 304 nuclear grade stainless steel in simulated PWR primary water[J]. PERGAMON-ELSEVIER SCIENCE LTD,2017,127:91-100. |
| APA | Deng, Ping.,Peng, Qunjia.,Han, En-Hou.,Ke, Wei.,Sun, Chen.,...&Peng, QJ .(2017).Effect of irradiation on corrosion of 304 nuclear grade stainless steel in simulated PWR primary water.PERGAMON-ELSEVIER SCIENCE LTD,127,91-100. |
| MLA | Deng, Ping,et al."Effect of irradiation on corrosion of 304 nuclear grade stainless steel in simulated PWR primary water".PERGAMON-ELSEVIER SCIENCE LTD 127(2017):91-100. |
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