Radiation damage in helium ion-irradiated reduced activation ferritic/martensitic steel
文献类型：期刊论文
| 作者 | Xia, L. D.1; Liu, W. B.1,2; Liu, H. P.3; Zhang, J. H.2; Chen, H.1; Yang, Z. G.1; Zhang, C.1 |
| 刊名 | NUCLEAR ENGINEERING AND TECHNOLOGY
 |
| 出版日期 | 2018-02-01 |
| 卷号 | 50页码:132-139 |
| 关键词 | Grain Boundary Helium Bubble Irradiation Temperature Reduced Activation Ferritic/Martensitic Steel |
| ISSN号 | 1738-5733 |
| DOI | 10.1016/j.net.2017.10.012 |
| 英文摘要 | Nanocrystalline reduced activation ferritic/martensitic (RAFM) steel samples were prepared using surface mechanical attrition treatment (SMAT). Un-SMATed and SMATed reduced activation ferritic/martensitic samples were irradiated by helium ions at 200 degrees C and 350 degrees C with 2 dpa and 8 dpa, respectively, to investigate the effects of grain boundaries (GBs) and temperature on the formation of He bubbles during irradiation. Experimental results show that He bubbles are preferentially trapped at GBs in all the irradiated samples. Bubble denuded zones are clearly observed near the GBs at 350 degrees C, whereas the bubble denuded zones are not obvious in the samples irradiated at 200 degrees C. The average bubble size increases and the bubble density decreases with an increasing irradiation temperature from 200 degrees C to 350 degrees C. Both the average size and density of the bubbles increase with an increasing irradiation dose from 2 dpa to 8 dpa. Bubbles with smaller size and lower density were observed in the SMATed samples but not in the un-SMATed samples irradiated in the same conditions, which indicate that GBs play an important role during irradiation, and sink strength increases as grain size decreases. (c) 2017 Korean Nuclear Society, Published by Elsevier Korea LLC. |
| WOS关键词 | AUSTENITIC STAINLESS-STEEL ; MARTENSITIC STEEL ; VOID FORMATION ; GRAIN-SIZE ; BCC FE ; NEUTRON ; MICROSTRUCTURE ; 1ST-PRINCIPLES ; MECHANISM ; EXPOSURE |
| 资助项目 | National Magnetic Confinement Fusion Energy Research Project[2015GB118001] ; China Postdoctoral Science Foundation[2015M582669] ; Fundamental Research Funds for the Central Universities ; [2016YFB0300104] |
| WOS研究方向 | Nuclear Science & Technology |
| 语种 | 英语 |
| WOS记录号 | WOS:000425255700014 |
| 出版者 | KOREAN NUCLEAR SOC |
| 资助机构 | National Magnetic Confinement Fusion Energy Research Project ; China Postdoctoral Science Foundation ; Fundamental Research Funds for the Central Universities |
| 源URL | [http://119.78.100.186/handle/113462/46306]  |
| 专题 | 中国科学院近代物理研究所 |
| 通讯作者 | Liu, W. B.; Zhang, C. |
| 作者单位 | 1.Tsinghua Univ, Minist Educ, Sch Mat Sci & Engn, Key Lab Adv Mat, Beijing 100084, Peoples R China 2.Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, Xian 710049, Shaanxi, Peoples R China 3.Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Gansu, Peoples R China |
| 推荐引用方式 GB/T 7714 | Xia, L. D.,Liu, W. B.,Liu, H. P.,et al. Radiation damage in helium ion-irradiated reduced activation ferritic/martensitic steel[J]. NUCLEAR ENGINEERING AND TECHNOLOGY,2018,50:132-139. |
| APA | Xia, L. D..,Liu, W. B..,Liu, H. P..,Zhang, J. H..,Chen, H..,...&Zhang, C..(2018).Radiation damage in helium ion-irradiated reduced activation ferritic/martensitic steel.NUCLEAR ENGINEERING AND TECHNOLOGY,50,132-139. |
| MLA | Xia, L. D.,et al."Radiation damage in helium ion-irradiated reduced activation ferritic/martensitic steel".NUCLEAR ENGINEERING AND TECHNOLOGY 50(2018):132-139. |
入库方式： OAI收割
来源：近代物理研究所
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