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Observation of fully detached divertor integrated with improved core confinement for tokamak fusion plasmas
Wang, H. Q.1; Wang, L.2; Ding, S.3; Garofalo, A. M.1; Gong, X. Z.2; Eldon, D.1; Guo, H. Y.1; Leonard, A. W.1; Hyatt, A. W.1; Qian, J. P.2; Weisberg, D. B.1; McClenaghan, J.1; Fenstermacher, M. E.4; Osborne, T. H.1; Lasnier, C. J.4; Watkins, J. G.5; Shafer, M. W.6; Grierson, B. A.7; Xu, G. S.2; Yan, Z.8; Mckee, G. R.8; Huang, J.2; Ren, J.9; Buttery, R. J.1; Humphreys, D. A.1; Thomas, D. M.1; Zhang, B.2; Liu, J. B.2
2021-05-01
发表期刊PHYSICS OF PLASMAS
ISSN1070-664X
通讯作者Wang, H. Q.(wanghuiqian@fusion.gat.com)
摘要Integration of divertor detachment with a high-performance (beta (N) similar to 3, beta (p) > 2, H-98 similar to 1.5) core plasma has been demonstrated in DIII-D high-beta (p) (poloidal beta) plasmas associated with a sustained core internal transport barrier (ITB) and an H-mode edge transport barrier (ETB). Such good core-edge integration has been achieved for both neon and nitrogen seeding, for both favorable and unfavorable B-field directions, independently from the impurity puffing locations, though these variations play important roles on divertor characteristics. Compared to the standard H-mode plasmas, the high-beta (p) plasma exhibits a much wider window of detachment compatible with high confinement core. Fully detached divertor plasmas with low plasma temperature (Te<5 eV), low particle flux, and low heat flux across the entire divertor target plate were obtained by using nitrogen seeding. This detached high-(p) plasma is compatible with a newly developed detachment control system which can help optimize the nitrogen gas flow rate. Several features, i.e., the high edge safety factor in the high-beta (p) scenario, impurity injection, closed divertor and reduced heating power requirement due to the high confinement, facilitate the achievement of full divertor detachment at lower density. Instead of degrading global performance, the divertor detachment facilitates the access to an even stronger ITB at large radius with a relatively weak ETB through self-organized synergy between ITB and ETB, leading to sustained high confinement. The strengthening of the large-radius ITB compensates for the ETB degradation associated with divertor detachment. In addition, a weak ETB naturally has smaller edge localized modes (ELMs). In particular, with neon injection, a long-period no-ELM H-mode phase has been achieved simultaneously with high-performance core and partially detached divertor plasmas. These results demonstrate the possibility of integrating excellent core plasma performance with an effective divertor solution, an essential step toward steady-state operation of reactor-grade plasmas.
DOI10.1063/5.0048428
关键词[WOS]ALCATOR C-MOD ; INTERNAL TRANSPORT BARRIER ; POWER EXHAUST ; PERFORMANCE ; PEDESTAL ; STABILITY ; RADIATION ; OPERATION ; GEOMETRY
收录类别SCI
语种英语
资助项目U.S. Department of Energy[DE-FC02-04ER54698] ; U.S. Department of Energy[DE-AC04-94AL85000] ; U.S. Department of Energy[DE-NA0003525] ; U.S. Department of Energy[DE-AC52-07NA27344] ; National Natural Science Foundation of China[11922513] ; National Natural Science Foundation of China[11775264] ; National Magnetic Confinement Fusion Science Program of China[2017YFE0301300] ; National Magnetic Confinement Fusion Science Program of China[2017YFE0300404] ; agency of the United States Government
项目资助者U.S. Department of Energy ; National Natural Science Foundation of China ; National Magnetic Confinement Fusion Science Program of China ; agency of the United States Government
WOS研究方向Physics
WOS类目Physics, Fluids & Plasmas
WOS记录号WOS:000678718800001
出版者AMER INST PHYSICS
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/334002/123171
专题中国科学院合肥物质科学研究院
通讯作者Wang, H. Q.
作者单位1.Gen Atom, POB 85608, San Diego, CA 92186 USA
2.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China
3.Oak Ridge Associated Univ, Oak Ridge, TN 37831 USA
4.Lawrence Livermore Natl Lab, Livermore, CA 94550 USA
5.Sandia Natl Labs, POB 969, Livermore, CA 94551 USA
6.Oak Ridge Natl Lab, POB 2008, Oak Ridge, TN 37831 USA
7.Princeton Univ, Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
8.Univ Wisconsin, Madison, WI 53706 USA
9.Univ Tennessee, Knoxville, TN 37996 USA
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GB/T 7714
Wang, H. Q.,Wang, L.,Ding, S.,et al. Observation of fully detached divertor integrated with improved core confinement for tokamak fusion plasmas[J]. PHYSICS OF PLASMAS,2021,28.
APA Wang, H. Q..,Wang, L..,Ding, S..,Garofalo, A. M..,Gong, X. Z..,...&Liu, J. B..(2021).Observation of fully detached divertor integrated with improved core confinement for tokamak fusion plasmas.PHYSICS OF PLASMAS,28.
MLA Wang, H. Q.,et al."Observation of fully detached divertor integrated with improved core confinement for tokamak fusion plasmas".PHYSICS OF PLASMAS 28(2021).
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