Scaling of divertor power footprint width in RF-heated type-III ELMy H-mode on the EAST superconducting tokamak

被引：64

作者：

Wang, L. ^{[1
,2
]}

Guo, H. Y. ^{[1
,3
]}

Xu, G. S. ^{[1
]}

Liu, S. C. ^{[1
]}

Gan, K. F. ^{[1
]}

Wang, H. Q. ^{[1
]}

Gong, X. Z. ^{[1
]}

Liang, Y. ^{[4
]}

Zou, X. L. ^{[5
]}

Hu, J. S. ^{[1
]}

Chen, L. ^{[1
]}

Xu, J. C. ^{[1
]}

Liu, J. B. ^{[1
]}

Yan, N. ^{[1
,6
]}

Zhang, W. ^{[1
]}

Chen, R. ^{[1
]}

Shao, L. M. ^{[1
]}

Ding, S. ^{[1
]}

Hu, G. H. ^{[1
]}

Feng, W. ^{[1
]}

Zhao, N. ^{[1
,2
]}

Xiang, L. Y. ^{[1
]}

Liu, Y. L. ^{[1
]}

Li, Y. L. ^{[1
]}

Sang, C. F. ^{[2
]}

Sun, J. Z. ^{[2
]}

Wang, D. Z. ^{[2
]}

Ding, H. B. ^{[2
]}

Luo, G. N. ^{[1
]}

Chen, J. L. ^{[1
]}

Gao, X. ^{[1
]}

Hu, L. Q. ^{[1
]}

Wan, B. N. ^{[1
]}

Li, J. ^{[1
]}

机构：

[1] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China

[2] Dalian Univ Technol, Sch Phys & Optoelect Technol, Dalian 116024, Peoples R China

[3] Tri Alpha Energy, Rancho Santa Margarita, CA 92688 USA

[4] Forschungszentrum Julich, Assoc EURATOM FZ Julich, Inst Energie & Klimaforsch PlasmaPhys, Trilateral Euregio Cluster, D-52425 Julich, Germany

[5] CEA, IRFM, F-13108 St Paul Les Durance, France

[6] Tech Univ Denmark, Assoc EURATOM RISO, Roskilde, Denmark

来源：

NUCLEAR FUSION | 2014年 / 54卷 / 11期

基金：

中国国家自然科学基金;

关键词：

power footprint width; divertor configurations; RF-heated scheme; EAST; SCRAPE-OFF LAYER; FLUX; TRANSPORT; TARGETS;

D O I：

10.1088/0029-5515/54/11/114002

中图分类号：

O35 [流体力学]; O53 [等离子体物理学];

学科分类号：

070204 ; 080103 ; 080704 ;

摘要：

Dedicated experiments for the scaling of divertor power footprint width have been performed in the ITER-relevant radio-frequency (RF)-heated H-mode scheme under the lower single null, double null and upper single null divertor configurations in the Experimental Advanced Superconducting Tokamak (EAST) under lithium wall coating conditioning. A strong inverse scaling of the edge localized mode (ELM)-averaged power fall-off width with the plasma current (equivalently the poloidal field) has been demonstrated for the attached type-III ELMy H-mode as lambda(q) proportional to I-p(-1.05) by various heat flux diagnostics including the divertor Langmuir probes (LPs), infra-red (IR) thermograph and reciprocating LPs on the low-field side. The IR camera and divertor LP measurements show that lambda(q,IR) approximate to lambda(q,div-LPs)/1.3 = 1.15 B-p,omp(-1.25), in good agreement with the multi-machine scaling trend during the inter-ELM phase between type-I ELMs or ELM-free enhanced D-alpha (EDA). H-mode. However, the magnitude is nearly doubled, which may be attributed to the different operation scenarios or heating schemes in EAST, i.e., dominated by electron heating. It is also shown that the type-III ELMs only broaden the power fall-off width slightly, and the ELM-averaged width is representative for the inter-ELM period. Furthermore, the inverse I-p (Bp) scaling appears to be independent of the divertor configurations in EAST. The divertor power footprint integral width, fall-off width and dissipation width derived from EAST IR camera measurements follow the relation, lambda(int) congruent to lambda(q) + 1.64S, yielding lambda(EAST)(int) = (1.39 +/- 0.03)lambda(EAST)(q) + (0.97 +/- 0.35) mm. Detailed analysis of these three characteristic widths was carried out to shed more light on their extrapolation to ITER.

引用

页数：9

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