Study of Irradiation Damage in Domestically Fabricated Nuclear Grade Stainless Steel
文献类型：期刊论文
| 作者 | Deng Ping1,3; Peng Qunjia3,4; Han En-Hou3; Ke Wei3; Sun Chen4; Xia Haihong4; Jiao Zhijie2 |
| 刊名 | ACTA METALLURGICA SINICA
 |
| 出版日期 | 2017-12-11 |
| 卷号 | 53期号:12页码:1588-1602 |
| 关键词 | nuclear grade stainless steel proton irradiation dislocation loop radiation-induced segregation radiation-induced hardening |
| ISSN号 | 0412-1961 |
| DOI | 10.11900/0412.1961.2017.00117 |
| 通讯作者 | Peng Qunjia(pengqunjia@yahoo.com) |
| 英文摘要 | The radiation-induced segregation (RIS) and microstructure evolution such as dislocation loops and cavities are major microstructural causes for the irradiation-assisted stress corrosion cracking (IASCC) of austenitic stainless steel (SS) core components. While a couple of studies have been reported on the irradiation induced damage in nuclear grade (NG) austenitic SS, the evolution of dislocation loop density and size and its correlation with the mechanical properties have still remained incompletely understood. In addition, the correlation between the segregation at the grain boundary and that at the dislocation loop has received limited attentions. In particular, there is still a lack of a systematic study of the irradiation damage in domestically fabricated NG austenitic SS. In this work, the proton-irradiation induced microstructural damage in domestically fabricated 304NG SS was characterized, in an effort to correlate the RIS and the dislocation loop density and size with the irradiation dose, as well as the dislocation loop density and size with the radiation-induced hardening. The results revealed that the radiationinduced microstructure damage was mainly dislocation loops with a few micro-voids. The loop density was in the order of 10(22) m(-3) with an average size of <10 nm. The square root of the product of loop density and size (Nd)(0.5), scaled linearly with the square root of irradiation dose with a factor of 6.8x10(3) dpa(-0.5) . mm(-1). The loops were believed to be mainly responsible for the hardening in 304NG SS, which also scaled linearly with (Nd)(0.5) with a factor of 1.16x10(-2) HV0.025 . mm. A comparative analysis about the segregation at the grain boundary and at the dislocation loop was conducted. While the depletion of Cr and enrichment of Ni at the dislocation loop and grain boundary showed no difference, the enrichment of Si at the dislocation loop could be of about 6 times of that at the grain boundary. In addition, the loop density and loop size, as well as RIS and radiation-induced hardening were all increased by a higher dose and tended to saturate by a dose of 3.0 similar to 5.0 dpa. |
| 资助项目 | International Science & Technology Cooperation Program of China[2014DFA50800] ; National Natural Science Foundation of China[51571204] |
| WOS研究方向 | Metallurgy & Metallurgical Engineering |
| 语种 | 英语 |
| WOS记录号 | WOS:000416301600005 |
| 出版者 | SCIENCE PRESS |
| 资助机构 | International Science & Technology Cooperation Program of China ; National Natural Science Foundation of China |
| 源URL | [http://ir.imr.ac.cn/handle/321006/125519]  |
| 专题 | 金属研究所_中国科学院金属研究所 |
| 通讯作者 | Peng Qunjia |
| 作者单位 | 1.Univ Sci & Technol China, Sch Mat Sci & Engn, Shenyang 110016, Liaoning, Peoples R China 2.Univ Michigan, Dept Nucl Engn & Radiol Sci, Ann Arbor, MI 48109 USA 3.Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Liaoning, Peoples R China 4.State Power Investment Corp, Res Inst, Beijing 102209, Peoples R China |
| 推荐引用方式 GB/T 7714 | Deng Ping,Peng Qunjia,Han En-Hou,et al. Study of Irradiation Damage in Domestically Fabricated Nuclear Grade Stainless Steel[J]. ACTA METALLURGICA SINICA,2017,53(12):1588-1602. |
| APA | Deng Ping.,Peng Qunjia.,Han En-Hou.,Ke Wei.,Sun Chen.,...&Jiao Zhijie.(2017).Study of Irradiation Damage in Domestically Fabricated Nuclear Grade Stainless Steel.ACTA METALLURGICA SINICA,53(12),1588-1602. |
| MLA | Deng Ping,et al."Study of Irradiation Damage in Domestically Fabricated Nuclear Grade Stainless Steel".ACTA METALLURGICA SINICA 53.12(2017):1588-1602. |
入库方式： OAI收割
来源：金属研究所
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