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

doi:10.1016/j.nme.2021.101050

	Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2
	Lu, Yudong 1,2,3; Ye, Minyou 1; Zhou, Guangming 2; Hernandez, Francisco A.2; Leppanen, Jaakko 4; Hu, Yuan 2,5
刊名	NUCLEAR MATERIALS AND ENERGY
	2021-09-01
卷号	28
关键词	Water cooled Lead Ceramic Breeder Neutronics Tritium breeding Serpent-2
DOI	10.1016/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
出版者	ELSEVIER
WOS记录号	WOS:000691545700010
资助机构	National Key Research, Development Program of China ; China Scholarship Council ; Euratom research and training programme 2014-2018 and 2019-2020
内容类型	期刊论文
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).