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Evaluation on the heat removal capacity of the first wall for water cooled breeder blanket of CFETR

文献类型：期刊论文

作者Jiang, Kecheng; Cheng, Xiaoman; Chen, Lei; Huang, Kai; Ma, Xuebin; Liu, Songlin
刊名FUSION ENGINEERING AND DESIGN
出版日期2016-02-01
卷号103期号:无页码:110-117
关键词Breeder Blanket First Wall Heat Removal Capacity
DOI10.1016/j.fusengdes.2015.12.025
文献子类Article
英文摘要The water cooled ceramic breeder blanket (WCCB) is being researched for Chinese Fusion Engineering Test Reactor (CFETR). As an important component of the blanket, the FW should satisfy with the thermal requirements in any case. In this paper, three parameters including the heat removal capacity, coolant pressure drop as well as the temperature rise of the FW were investigated under different coolant velocity and heat flux from the plasma. Using the same first wall structure, two main water cooled schemes including Boiling Water Reactor (BWR, 7 MPa pressure and 265 degrees C temperature inlet) and Pressurized Water Reactor (PWR, 15 MPa pressure and 285 degrees C temperature inlet) conditions are discussed in the thermal hydraulic calculation. For further research, the thermal hydraulic characteristics of using helium as coolant (8 MPa pressure, 300 degrees C temperature inlet) are also explored to provide CFETR blanket design with more useful data supports. Without regard to the outlet coolant condition requirements of the blanket, the results indicate that the ultimate heat flux that the FW can resist is 2.2 MW/m(2) at velocity of 5 m/s for BWR, 2.0 MW/m(2) at velocity of 5 m/s for PWR and 0.87 MW/m(2) for helium at velocity 100 m/s under the chosen operation condition. The detrimental departure from nucleate boiling (DNB) crisis would occur at the velocity of 1 m/s under the heat flux of 3 MW/m(2) and dry out crisis appears at the velocity of less than 0.2 m/s with the heat flux of more than 1 MW/m(2) for BWR. The further blanket/FW optimization design is provided with more useful data references according to the abundant calculation results. (c) 2015 Elsevier B.V. All rights reserved.
WOS关键词FLOW
WOS研究方向Nuclear Science & Technology
语种英语
WOS记录号WOS:000371188300015
资助机构National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; National Magnetic Confinement Fusion Science Program of China(2013GB108004 ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000) ; 2014GB122000)
源URL[http://ir.hfcas.ac.cn:8080/handle/334002/21760]  
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Chinese Acad Sci, Inst Plasma Phys, ShuShanHu Rd 350, Hefei 230031, Anhui, Peoples R China
推荐引用方式
GB/T 7714		 Jiang, Kecheng,Cheng, Xiaoman,Chen, Lei,et al. Evaluation on the heat removal capacity of the first wall for water cooled breeder blanket of CFETR[J]. FUSION ENGINEERING AND DESIGN,2016,103(无):110-117.
APA Jiang, Kecheng,Cheng, Xiaoman,Chen, Lei,Huang, Kai,Ma, Xuebin,&Liu, Songlin.(2016).Evaluation on the heat removal capacity of the first wall for water cooled breeder blanket of CFETR.FUSION ENGINEERING AND DESIGN,103(无),110-117.
MLA Jiang, Kecheng,et al."Evaluation on the heat removal capacity of the first wall for water cooled breeder blanket of CFETR".FUSION ENGINEERING AND DESIGN 103.无(2016):110-117.

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来源：合肥物质科学研究院

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