Evaluation of tritium burnup fraction for CFETR scenarios with core-edge coupling simulations

doi:10.1088/1741-4326/ab742b

HFCAS OpenIR

	Evaluation of tritium burnup fraction for CFETR scenarios with core-edge coupling simulations
	Xie, Hai 1,2,3; Chan, Vincent S.4; Ding, Rui3 ; Shi, Nan3 ; Jian, Xiang 5; Zagorski, Roman 6; Ivanova-Stanik, Irena 7; Chen, Jiale3 ; Chen, Junling3 ; Li, Jiangang1,3
	2020-04-01
发表期刊	NUCLEAR FUSION
ISSN	0029-5515
通讯作者	Ding, Rui(rding@ipp.ac.cn)
摘要	A key mission for the next-step fusion tokamak device China Fusion Engineering Test Reactor (CFETR) is demonstrating tritium self-sufficiency, which requires a sufficiently high tritium burnup fraction (f(burnup)) in order to match a practically achievable tritium breeding ratio (TBR) with the blanket design constraints. Core-edge coupling simulations are performed to investigate the dependence of f(burnup) on different controlling parameters for CFETR scenarios. Core plasma profiles with a range of pedestal densities are simulated by consistent iterative calculations of equilibrium, transport, auxiliary heating and current drives within the OMFIT framework. The core-SOL integrated COREDIV code is then used to evaluate f(burnup) with the OMFIT modelled core plasma parameters as input. According to the simulations, f(burnup) can be effectively increased with a higher pedestal density on account of the fusion power increasing faster than the fueling source required to maintain steady-state. Higher can also increase the f(burnup) due to increase of fuel recycling. Deeper pellet fueling deposition and lower ratio of particle to thermal diffusivities D/chi can both increase the effective particle confinement time and thus f(burnup). However, the effect of helium and other impurities (Ar and W) is shown to reduce f(burnup) for comparable impurity and main ion transport. Based on our analysis, using present pellet fueling technology, achieving f(burnup) > 3% for CFETR will be very challenging. This is a lower limit for the required TBR (>1) to match the achievable TBR for tritium self-sufficiency. Furthermore, our study suggests that if fueling can penetrate deeper than r/a < 0.8 under optimistic conditions, the required burnup fraction could be attainable. The modelling results thus provide important suggestions and implications for the optimization of CFETR scenarios and development of advanced fueling systems.
关键词	CFETR tritium burnup fraction core-edge simulations
DOI	10.1088/1741-4326/ab742b
关键词[WOS]	SELF-SUFFICIENCY ; FUEL-CYCLE ; CONFINEMENT ; TECHNOLOGY ; INVENTORY ; EXHAUST ; BALANCE
收录类别	SCI
语种	英语
资助项目	National Key Research and Development Program of China[2017YFE0301300] ; National Key Research and Development Program of China[2017YFE0300500] ; National Key Research and Development Program of China[2017YFA0402500] ; National Nature Science Foundation of China[11675218] ; National Nature Science Foundation of China[11675219] ; National Nature Science Foundation of China[11861131010] ; National Nature Science Foundation of China[11705238] ; CASHIPS Director's Fund[BJPY2019B01] ; Key Research Program of Frontier Sciences, CAS[ZDBS-LY-SLH010] ; Shenzhen Clean Energy Research Institute
项目资助者	National Key Research and Development Program of China ; National Nature Science Foundation of China ; CASHIPS Director's Fund ; Key Research Program of Frontier Sciences, CAS ; Shenzhen Clean Energy Research Institute
WOS研究方向	Physics
WOS类目	Physics, Fluids & Plasmas
WOS记录号	WOS:000519799800001
出版者	IOP PUBLISHING LTD
引用统计	被引频次：13[WOS] [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	http://ir.hfcas.ac.cn:8080/handle/334002/103808
专题	中国科学院合肥物质科学研究院
通讯作者	Ding, Rui
作者单位	1.Shenzhen Univ, Adv Energy Res Ctr, Shenzhen 518060, Peoples R China 2.Shenzhen Univ, Coll Optoelect Engn, Minist Educ & Guangdong Prov, Key Lab Optoelect Devices & Syst, Shenzhen 518060, Peoples R China 3.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China 4.Univ Sci & Technol China, Sch Phys Sci, Dept Engn & Appl Phys, Hefei 230031, Anhui, Peoples R China 5.Univ Calif San Diego, Energy Res Ctr, La Jolla, CA 92093 USA 6.Natl Ctr Nucl Res, PL-05400 Otwock, Poland 7.Inst Plasma Phys & Laser Microfus, Hery Str 23, PL-01497 Warsaw, Poland
第一作者单位	中科院等离子体物理研究所
通讯作者单位	中科院等离子体物理研究所
推荐引用方式 GB/T 7714	Xie, Hai,Chan, Vincent S.,Ding, Rui,et al. Evaluation of tritium burnup fraction for CFETR scenarios with core-edge coupling simulations[J]. NUCLEAR FUSION,2020,60.
APA	Xie, Hai.,Chan, Vincent S..,Ding, Rui.,Shi, Nan.,Jian, Xiang.,...&Li, Jiangang.(2020).Evaluation of tritium burnup fraction for CFETR scenarios with core-edge coupling simulations.NUCLEAR FUSION,60.
MLA	Xie, Hai,et al."Evaluation of tritium burnup fraction for CFETR scenarios with core-edge coupling simulations".NUCLEAR FUSION 60(2020).