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Scaling of L-mode heat flux for ITER and COMPASS-U divertors, based on five tokamaks | |
Horacek, J.1; Adamek, J.1; Komm, M.1; Seidl, J.1; Vondracek, P.1; Jardin, A.2,3; Guillemaut, Ch4; Elmore, S.5; Thornton, A.5; Jirakova, K.1,6; Jaulmes, F.1; Deng, G.7,8,9; Gao, X.7,8; Wang, L.7,8,10; Ding, R.7; Brunner, D.11,12; LaBombard, B.12; Olsen, J.13; Rasmussen, J. J.13; Nielsen, A. H.13; Naulin, V13; Ezzat, M.14,15; Camacho, K. M.16; Hron, M.1; Matthew, G. F.5 | |
2020-06-01 | |
发表期刊 | NUCLEAR FUSION |
ISSN | 0029-5515 |
通讯作者 | Horacek, J.(horacek@ipp.cas.cz) |
摘要 | This contribution aims to improve existing scalings of the L-mode power decay length.omp q, especially for plasma configurations with strike points at the ITER-relevant location-closed vertical divertor targets. We propose 13 new.omp q scalings based on data from the tokamaks JET, EAST, MAST, Alcator C-mod and COMPASS, and validate them against the output of the 2D turbulence code HESEL. The analysis covers 500 divertor heat flux profiles (obtained by probes or IR cameras), measured in L-mode discharges with varying 12 global plasma parameters (all well predictable). We find that the two previously published scalings (Eich 2013 J. Nucl. Mat. 438 S72) and (Scarabosio 2013 J. Nucl. Mat. 438 S426), which were based on outer target data from AUG and JET, describe the JET, C-mod and COMPASS profiles well. This holds not only at the outer horizontal and vertical targets, but surprisingly also at the inner vertical targets. In contrast, EAST, HESEL and especially MAST data are poorly described by these two scalings. We therefore derive 13 new scalings, which account for 85-92 % of the measured.omp q variability across all five tokamaks. Although each of the scalings is based on a different parameter combination, their predictions for the ITER and COMPASS-Upgrade tokamaks are very similar. Just before the L-H transition in the ITER baseline scenario, the presented scalings predict values.omp q = 3.0 +/- 0.5 mm. For the COMPASS-Upgrade tokamak, all the scalings predict.omp q = 2.1 +/- 0.5 mm with a single exception of the scaling based on the stored plasma energy which predicts only 1.2 mm for both tokamaks. We encourage the reader to use as many of these scalings as possible, depending on available data. In attached plasma and using significant assumptions, our results imply steady-state surface-perpendicular heat flux around 10 MW/m2 for ITER, and 20 MW/m2 for COMPASS-Upgrade. |
关键词 | tokamak L-mode divertor scaling heat flux ITER COMPASS-Upgrade |
DOI | 10.1088/1741-4326/ab7e47 |
关键词[WOS] | ASDEX-UPGRADE ; THERMOGRAPHY ; WIDTH |
收录类别 | SCI |
语种 | 英语 |
资助项目 | Czech Science Foundation[GA19-15229S] ; Czech Science Foundation[MEYS LM2015045] ; Czech Science Foundation[EF16_013/0001551] ; US DoE[DESC0014264] ; US DoE[DE-FC02-99ER54512] ; Euratom research and training program 2014-2018[633053] ; Euratom research and training program 2019-2020[633053] ; European Union |
项目资助者 | Czech Science Foundation ; US DoE ; Euratom research and training program 2014-2018 ; Euratom research and training program 2019-2020 ; European Union |
WOS研究方向 | Physics |
WOS类目 | Physics, Fluids & Plasmas |
WOS记录号 | WOS:000535881300001 |
出版者 | IOP PUBLISHING LTD |
引用统计 | |
文献类型 | 期刊论文 |
条目标识符 | http://ir.hfcas.ac.cn:8080/handle/334002/103212 |
专题 | 中国科学院合肥物质科学研究院 |
通讯作者 | Horacek, J. |
作者单位 | 1.CAS, Inst Plasma Phys, Za Slovankou 3, Prague, Czech Republic 2.CEA, IRFM, F-13108 St Paul Les Durance, France 3.Polish Acad Sci, Inst Nucl Phys, PL-31342 Krakow, Poland 4.Univ Lisbon, Inst Plasmas & Fusao Nucl, IST, Lisbon, Portugal 5.Culham Sci Ctr, UKAEA, Abingdon OX14 3DB, Oxon, England 6.Czech Tech Univ, FNSPE, Prague, Czech Republic 7.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China 8.Univ Sci & Technol China, Hefei 230026, Peoples R China 9.Lawrence Livermore Natl Lab, Livermore, CA 94550 USA 10.Dalian Univ Technol, Sch Phys & Optoelect, Dalian, Peoples R China 11.Commonwealth Fus Syst, Cambridge, MA USA 12.MIT, Plasma Sci & Fus Ctr, 77 Massachusetts Ave, Cambridge, MA 02139 USA 13.Tech Univ Denmark, Dept Phys, PPFE, Bldg 309, DK-2800 Lyngby, Denmark 14.Univ Carlos III Madrid, Av Univ 30, Madrid 28911, Spain 15.Mansoura Univ, Fac Sci, Phys Dept, Mansoura 35516, Egypt 16.Univ Lorraine, Nancy, Meurthe Moselle, France |
推荐引用方式 GB/T 7714 | Horacek, J.,Adamek, J.,Komm, M.,et al. Scaling of L-mode heat flux for ITER and COMPASS-U divertors, based on five tokamaks[J]. NUCLEAR FUSION,2020,60. |
APA | Horacek, J..,Adamek, J..,Komm, M..,Seidl, J..,Vondracek, P..,...&Matthew, G. F..(2020).Scaling of L-mode heat flux for ITER and COMPASS-U divertors, based on five tokamaks.NUCLEAR FUSION,60. |
MLA | Horacek, J.,et al."Scaling of L-mode heat flux for ITER and COMPASS-U divertors, based on five tokamaks".NUCLEAR FUSION 60(2020). |
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