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Chinese Academy of Sciences Institutional Repositories Grid
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  2. 合肥物质科学研究院
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  4. 中科院等离子体物理研究所
Investigation of wetting property between liquid lead lithium alloy and several structural materials for Chinese DEMO reactor

文献类型：期刊论文

作者Lu, Wei1; Wang, Weihua1,2; Jiang, Haiyan3; Zuo, Guizhong2; Pan, Baoguo1; Xu, Wei2; Chu, Delin1; Hu, Jiansheng2; Qi, Junli1,2
刊名JOURNAL OF NUCLEAR MATERIALS
出版日期2017-10-01
卷号494页码:303-310
关键词Lead Lithium Rafm Sic 316l Wetting Property Contact Angles Corrosion
DOI10.1016/j.jnucmat.2017.07.055
文献子类Article
英文摘要The dual-cooled lead lithium (PbLi) blanket is considered as one of the main options for the Chinese demonstration reactor (DEMO). Liquid PbLi alloy is used as the breeder material and coolant. Reduced activation ferritic/martensitic (RAFM) steel, stainless steel and the silicon carbide ceramic matrix composite (SiCf) are selected as the substrate materials for different use. To investigate the wetting property and inter-facial interactions of PbLi/RAFM steel, PbLi/SS316L, PbLi/SiC and PbLi/SiCf couples, in this paper, the special vacuum experimental device is built, and the 'dispensed droplet' modification for the classic sessile droplet technique is made. Contact angles are measured between the liquid PbLi and the various candidate materials at blanket working temperature from 260 to 480 degrees C. X-ray photoelectron spectroscopy (XPS) is used to characterize the surface components of PbLi droplets and substrate materials, in order to study the element trans-port and corrosion mechanism. Results show that SiC composite (Sic(f)) and SiC ceramic show poor wetting properties with the liquid PbLi alloy. Surface roughness and testing temperature only provide tiny improvements on the wetting property below 480 degrees C. RAFM steel performs better wetting properties and corrosion residence when contacted with molten PbLi, while SS316L shows low corrosion residence above 420 degrees C for the decomposition of protective surface film mainly consisted of chromic sesquioxide. The results could provide meaningful compatibility database of liquid PbLi alloy and valuable reference in engineering design of candidate structural and functional materials for future fusion blanket. (C) 2017 Elsevier B.V. All rights reserved.
WOS关键词RAFM STEEL ; NICKEL ; PB
WOS研究方向Materials Science ; Nuclear Science & Technology
语种英语
WOS记录号WOS:000410561200034
资助机构National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; 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National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Magnetic Confinement Fusion Science Program of China(2013GB113004 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; National Natural Science Foundation of China(51576208 ; 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源URL[http://ir.hfcas.ac.cn:8080/handle/334002/33661]  
专题合肥物质科学研究院_中科院等离子体物理研究所
作者单位1.Army Officer Acad, Inst Appl Phys, Hefei 230031, Anhui, Peoples R China
2.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China
3.Hefei Univ Technol, Sch Mat Sci & Engn, Hefei 230009, Anhui, Peoples R China
推荐引用方式
GB/T 7714		 Lu, Wei,Wang, Weihua,Jiang, Haiyan,et al. Investigation of wetting property between liquid lead lithium alloy and several structural materials for Chinese DEMO reactor[J]. JOURNAL OF NUCLEAR MATERIALS,2017,494:303-310.
APA Lu, Wei.,Wang, Weihua.,Jiang, Haiyan.,Zuo, Guizhong.,Pan, Baoguo.,...&Qi, Junli.(2017).Investigation of wetting property between liquid lead lithium alloy and several structural materials for Chinese DEMO reactor.JOURNAL OF NUCLEAR MATERIALS,494,303-310.
MLA Lu, Wei,et al."Investigation of wetting property between liquid lead lithium alloy and several structural materials for Chinese DEMO reactor".JOURNAL OF NUCLEAR MATERIALS 494(2017):303-310.

入库方式： OAI收割

来源：合肥物质科学研究院

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