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Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2

文献类型：期刊论文

作者Lu, Yudong1,2,3; Ye, Minyou1; Zhou, Guangming2; Hernandez, Francisco A.2; Leppanen, Jaakko4; Hu, Yuan2,5
刊名NUCLEAR MATERIALS AND ENERGY
出版日期2021-09-01
卷号28
关键词Water cooled Lead Ceramic Breeder Neutronics Tritium breeding Serpent-2
DOI10.1016/j.nme.2021.101050
通讯作者Ye, Minyou(yemy@ustc.edu.cn) ; Zhou, Guangming(guangming.zhou@kit.edu)
英文摘要Innovative Water cooled Lead Ceramic Breeder (WLCB) blanket concepts are being developed at Karlsruhe Institute of Technology (KIT) to explore alternative options for the European demonstration fusion power plant (DEMO). Compared to the Helium Cooled Pebble Bed blanket (HCPB, which is one of the two driver blanket concepts of the European DEMO), Lead/ Lead-alloy is used as neutron multiplier instead of Be/Be-alloy and pressurized subcooled water is used as coolant instead of Helium in the WLCB. The tritium self-sufficiency is the vital function that a Breeding Blanket has to achieve. The absorption of neutrons by water leads to a decrease in the number of neutrons, so the requirement to improve the tritium breeding capacity of the water-cooled blankets is particularly prominent. The Monte Carlo neutron transport code Serpent-2 developed by VTT in Finland has already been benchmarked to be applicable to neutronics calculations in the fusion reactors in a previous study. In this paper, an exploratory TBR study on Water cooled Lead Ceramic Breeder Blanket is presented.
资助项目National Key Research, Development Program of China[2017YFE0301501] ; National Key Research, Development Program of China[2017YFE0301305] ; China Scholarship Council[201806340163] ; Euratom research and training programme 2014-2018 and 2019-2020[633053]
WOS研究方向Nuclear Science & Technology
语种英语
WOS记录号WOS:000691545700010
出版者ELSEVIER
资助机构National Key Research, Development Program of China ; China Scholarship Council ; Euratom research and training programme 2014-2018 and 2019-2020
源URL[http://ir.hfcas.ac.cn:8080/handle/334002/125227]  
专题中国科学院合肥物质科学研究院
通讯作者Ye, Minyou; Zhou, Guangming
作者单位1.Univ Sci & Technol China, Sch Nucl Sci & Technol, Hefei 230026, Peoples R China
2.Karlsruhe Inst Technol KIT, D-76344 Eggenstein Leopoldshafen, Germany
3.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China
4.VTT Tech Res Ctr Finland, FI-02150 Espoo, Finland
5.Peking Univ, Sch Phys, State Key Lab Nucl Phys & Technol, Beijing 100871, Peoples R China
推荐引用方式
GB/T 7714		 Lu, Yudong,Ye, Minyou,Zhou, Guangming,et al. Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2[J]. NUCLEAR MATERIALS AND ENERGY,2021,28.
APA Lu, Yudong,Ye, Minyou,Zhou, Guangming,Hernandez, Francisco A.,Leppanen, Jaakko,&Hu, Yuan.(2021).Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2.NUCLEAR MATERIALS AND ENERGY,28.
MLA Lu, Yudong,et al."Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2".NUCLEAR MATERIALS AND ENERGY 28(2021).

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来源：合肥物质科学研究院

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