| PHYSICS OF GASES, PLASMAS, AND ELECTRIC DISCHARGES |
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Heat Flux on EAST Divertor Plate in H-mode with LHCD/LHCD+NBI |
| Bo Shi1,2,3, Zhen-Dong Yang4, Bin Zhang1, Cheng Yang1, Kai-Fu Gan1, Mei-Wen Chen1, Jin-Hong Yang3, Hui Zhang3, Jun-Li Qi3, Xian-Zu Gong1, Xiao-Dong Zhang1, Wei-Hua Wang1,3** |
1Institute of Plasma Physics, Hefei Institutes of Physical Sciences, Chinese Academy of Sciences, Hefei 230031
2Science Island Branch of Graduate School, University of Science and Technology of China, Hefei 230031
3Institute of Applied Physics, Army Officer Academy, Hefei 230031
4Teaching and Research Department of Physics, Tongling University, Tongling 244000
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| Cite this article: |
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Bo Shi, Zhen-Dong Yang, Bin Zhang et al 2017 Chin. Phys. Lett. 34 095201 |
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Abstract Based on the surface temperature measured by the infrared camera on the experimental advanced superconducting tokamak (EAST), the heat fluxes on the lower outer divertor target plate during H-mode with the lower-hybrid wave current drive (LHCD) only and with the LHCD combined with the neutral beam injection (NBI) are calculated by the DFLUX code and compared. The analyzed discharges are lower single null divertor configuration discharges. In the case with the LHCD only ($I_{\rm p}\sim 400$ kA, $P_{\rm LHCD}\sim2$ MW), ELM-free appears after L-H transition with the peak heat flux on the lower outer target plate less than 1 MW/m$^{2}$. However, there is no ELM-free appearing after the L-H transition in the case with the LHCD+NBI ($I_{\rm p}\sim300$ kA, $P_{\rm LHCD}+P_{\rm NBI}\sim2$ MW). The results show that the peak heat fluxes on the lower outer target plate in the LHCD+NBI H-mode cases are larger than those in the LHCD H-mode under the similar auxiliary heating power. This is because the heat flux profiles of the lower outer target plate as a function of plate location in ELMing with the LHCD+NBI are narrower than those with the LHCD only. The results are consistent with the results in terms of the scrape-off layer width observed in the EAST.
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Received: 17 March 2017
Published: 15 August 2017
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| PACS: |
52.55.Fa
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(Tokamaks, spherical tokamaks)
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52.55.Rk
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(Power exhaust; divertors)
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| Fund: Supported by the National Natural Science Foundation of China under Grant Nos 11505290, 51576208 and 11575239, and the National Magnetic Confinement Fusion Science Program of China under Grant Nos 2013GB113004 and 2015GB102004. |
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