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Achievements of actively controlled divertor detachment compatible with sustained high confinement core in DIII-D and EAST
Wang, L.1; Wang, H. Q.2; Eldon, D.2; Yuan, Q. P.1; Ding, S.1,3; Li, K. D.1; Garofalo, A. M.2; Gong, X. Z.1; Xu, G. S.1; Guo, H. Y.2; Wu, K.1; Meng, L. Y.1; Xu, J. C.1; Liu, J. B.1; Chen, M. W.1; Zhang, B.1; Duan, Y. M.1; Ding, F.1; Yang, Z. S.1; Qian, J. P.1; Huang, J.1; Ren, Q. L.1; Leonard, A. W.2; Fenstermacher, M.4; Lasnier, C.4; Watkins, J. G.5; Shafer, M. W.6; Barr, J.2; Weisberg, D.2; McClenaghan, J.2; Hanson, J.7; Hyatt, A.2; Osborne, T.2; Thomas, D.2; Humphreys, D.2; Buttery, R. J.2; Luo, G-N1; Xiao, B. J.1; Wan, B. N.1; Li, J. G.1
2022-07-01
Source PublicationNUCLEAR FUSION
ISSN0029-5515
Corresponding AuthorWang, L.(lwang@ipp.ac.cn) ; Wang, H. Q.(wanghuiyian@fusion.gat.com)
AbstractThe compatibility of efficient divertor detachment with high-performance core plasma is vital to the development of magnetically controlled fusion energy. The joint research on the EAST and DIII-D tokamaks demonstrates successful integration of divertor detachment with excellent core plasma confinement quality, a milestone towards solving the critical plasma-wall-interaction (PWI) issue and core-edge integration for ITER and future reactors. In EAST, actively controlled partial detachment with T (et,div) similar to 5 eV around the strike point and H (98) > 1 in different H-mode scenarios including the high beta (P) H-mode scenario have been achieved with ITER-like tungsten divertor, by optimizing the detachment access condition and performing detailed experiments for core-edge integration. For active long-pulse detachment feedback control, a 30 s H-mode operation with detachment-control duration being 25 s has been successfully achieved in EAST. DIII-D has achieved actively controlled fully detached divertor with low plasma electron temperature (T (et,div) <= 5 eV across the entire divertor target) and low particle flux (degree of detachment, DoD > 3), simultaneously with very high core performance (beta (N) similar to 3, beta (P) > 2 and H (98) similar to 1.5) in the high beta(P) scenario being developed for ITER and future reactors. The high-beta (P) high confinement scenario is characterized by an internal transport barrier (ITB) at large radius and a weak edge transport barrier (ETB, or pedestal), which are synergistically self-organized. Both the high-beta (P) scenario and impurity seeding facilitate divertor detachment. The detachment access leads to the reduction of ETB, which facilitates the development of an even stronger ITB at large radius in the high beta (P) scenario. Thus, this strong large radius ITB enables the core confinement improvement during detachment. These significant joint DIII-D and EAST advances on the compatibility of high confinement core and detached divertor show a great potential for achieving a high-performance core plasma suitable for long-pulse operation of fusion reactors with controllable steady-state PWIs.
Keyworddivertor detachment core-edge integration active control EAST DIII-D
DOI10.1088/1741-4326/ac4774
Indexed BySCI
Language英语
Funding ProjectNational Magnetic Confinement Fusion Science Program of China[2017YFE0301300] ; National Magnetic Confinement Fusion Science Program of China[2017YFA0402500] ; National Magnetic Confinement Fusion Science Program of China[2017YFE0300404] ; National Magnetic Confinement Fusion Science Program of China[2019YFE03030000] ; National Natural Science Foundation of China[11922513] ; National Natural Science Foundation of China[11775264] ; US Department of Energy, Office of Science, Office of Fusion Energy Sciences[DE-FC02-04ER54698] ; US Department of Energy, Office of Science, Office of Fusion Energy Sciences[DE-AC04-94AL85000] ; US Department of Energy, Office of Science, Office of Fusion Energy Sciences[DE-NA0003525] ; US Department of Energy, Office of Science, Office of Fusion Energy Sciences[DE-AC52-07NA27344]
Funding OrganizationNational Magnetic Confinement Fusion Science Program of China ; National Natural Science Foundation of China ; US Department of Energy, Office of Science, Office of Fusion Energy Sciences
WOS Research AreaPhysics
WOS SubjectPhysics, Fluids & Plasmas
WOS IDWOS:000785594100001
PublisherIOP Publishing Ltd
Citation statistics
Document Type期刊论文
Identifierhttp://ir.hfcas.ac.cn:8080/handle/334002/128484
Collection中国科学院合肥物质科学研究院
Corresponding AuthorWang, L.; Wang, H. Q.
Affiliation1.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China
2.Gen Atom, POB 85608, San Diego, CA 92186 USA
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.Columbia Univ, Dept Appl Math & Appl Phys, New York, NY 10027 USA
First Author AffilicationChinese Academy of Sciences, Institute of Plasma Physics, Hefei 230031, Anhui, Peoples R China
Corresponding Author AffilicationChinese Academy of Sciences, Institute of Plasma Physics, Hefei 230031, Anhui, Peoples R China
Recommended Citation
GB/T 7714
Wang, L.,Wang, H. Q.,Eldon, D.,et al. Achievements of actively controlled divertor detachment compatible with sustained high confinement core in DIII-D and EAST[J]. NUCLEAR FUSION,2022,62.
APA Wang, L..,Wang, H. Q..,Eldon, D..,Yuan, Q. P..,Ding, S..,...&Li, J. G..(2022).Achievements of actively controlled divertor detachment compatible with sustained high confinement core in DIII-D and EAST.NUCLEAR FUSION,62.
MLA Wang, L.,et al."Achievements of actively controlled divertor detachment compatible with sustained high confinement core in DIII-D and EAST".NUCLEAR FUSION 62(2022).
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