Integrated modeling of CFETR hybrid scenario plasmas

doi:10.1088/1741-4326/abd7b8

	Integrated modeling of CFETR hybrid scenario plasmas
	Chen, Jiale 1; Chan, Vincent S.2,3; Jian, Xiang 4; Zhang, Xinjun 1; Ren, Qilong 1; Li, Guoqiang 1; Zhou, Chengxi 5
刊名	NUCLEAR FUSION
	2021-04-01
卷号	61
关键词	integrated modeling CFETR hybrid scenario for tokamak fusion reactor turbulent transport heating and current drive particle transport
ISSN号	0029-5515
DOI	10.1088/1741-4326/abd7b8
通讯作者	Chen, Jiale(chen@ipp.cas.cn)
英文摘要	Demonstration of DEMO relevant fusion power (P-fus) level and tritium self-sufficiency are two important goals of the China fusion engineering testing reactor (CFETR). In this work the integrated modeling including self-consistent core-pedestal coupling are used to design the hybrid scenario plasmas at flat-top phase for these goals. Such plasmas have been taken as the reference plasma for studying the compatibility of the hybrid scenario with CFETR engineering design in the past two years. The physics justification for the selection of plasma density, Z(eff), safety factor profile, and in particular the choice of auxiliary heating and current drive is presented. According to a scan of plasma density and Z(eff), the target of P-fus approximate to 1 GW and finite ohmic flux consumption increment phi(ohm) (4 h) <= 250 Vs can be met with Z(eff) = 1.9-2.2 and the density at the pedestal top set at 90% of the Greenwald limit. Turbulent transport analysis using the gyro-Landau-fluid model TGLF shows that the electromagnetic effects can enhance the energy confinement but reduce the particle confinement and thus P-fus. A baseline hybrid scenario case matching the target in the concept design is built using a combination of neutral beams (NB) and electron cyclotron (EC) waves to flatten the safety factor profile in the deep core region (with the normalized plasma radius rho <= 0.4). Such profile can yield better particle and energy confinement than that with either higher magnetic shear in the deep core region or higher q value in outer core region (e.g., due to the addition of lower hybrid current drive). Switching a part of auxiliary heating from electron to ions, e.g., replacing a part of EC waves by waves in the ion cyclotron range of frequencies, reduces the particle confinement and thus P-fus. Since high harmonic fast waves (HHFW) can drive current at the same location as ECCD with higher current drive efficiency than ECCD and yield more electron heating than NB, the case using HHFW to replace a part of EC waves and NB can yield higher P-fus and lower increment phi(ohm) than the baseline case. A discussion is given on future simulations to explore the improvement in plasma performance and the broadening of the feasible design space.
资助项目	National Key Research and Development Program of China[2017YFE0300500] ; National Key Research and Development Program of China[2017YFE0300501]
WOS研究方向	Physics
语种	英语
出版者	IOP PUBLISHING LTD
WOS记录号	WOS:000624474300001
资助机构	National Key Research and Development Program of China
内容类型	期刊论文
源URL	[http://ir.hfcas.ac.cn:8080/handle/334002/120514]
专题	中国科学院合肥物质科学研究院
通讯作者	Chen, Jiale
作者单位	1.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China 2.Univ Sci & Technol China, Sch Phys Sci, Dept Engn & Appl Phys, Hefei 230026, Peoples R China 3.Gen Atom, POB 85608, San Diego, CA 92186 USA 4.Univ Calif San Diego, Energy Res Ctr, La Jolla, CA 92093 USA 5.Huazhong Univ Sci & Technol, Sch Elect & Elect Engn, State Key Lab Adv Electromagnet Engn & Technol, Wuhan 430074, Peoples R China
推荐引用方式 GB/T 7714	Chen, Jiale,Chan, Vincent S.,Jian, Xiang,et al. Integrated modeling of CFETR hybrid scenario plasmas[J]. NUCLEAR FUSION,2021,61.
APA	Chen, Jiale.,Chan, Vincent S..,Jian, Xiang.,Zhang, Xinjun.,Ren, Qilong.,...&Zhou, Chengxi.(2021).Integrated modeling of CFETR hybrid scenario plasmas.NUCLEAR FUSION,61.
MLA	Chen, Jiale,et al."Integrated modeling of CFETR hybrid scenario plasmas".NUCLEAR FUSION 61(2021).