Scaling of L-mode heat flux for ITER and COMPASS-U divertors, based on five tokamaks
文献类型：期刊论文
| 作者 | Horacek, J.16; Adamek, J.16; Komm, M.16; Seidl, J.16; Vondracek, P.16; Jardin, A.14,15; Guillemaut, Ch13; Elmore, S.12; Thornton, A.12; Jirakova, K.11,16 |
| 刊名 | NUCLEAR FUSION
 |
| 出版日期 | 2020-06-01 |
| 卷号 | 60 |
| ISSN号 | 0029-5515 |
| 关键词 | tokamak L-mode divertor scaling heat flux ITER COMPASS-Upgrade |
| DOI | 10.1088/1741-4326/ab7e47 |
| 通讯作者 | Horacek, J.(horacek@ipp.cas.cz) |
| 英文摘要 | 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. |
| WOS关键词 | ASDEX-UPGRADE ; THERMOGRAPHY ; WIDTH |
| 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 |
| WOS研究方向 | Physics |
| 语种 | 英语 |
| 出版者 | IOP PUBLISHING LTD |
| WOS记录号 | WOS:000535881300001 |
| 资助机构 | Czech Science Foundation ; US DoE ; Euratom research and training program 2014-2018 ; Euratom research and training program 2019-2020 ; European Union |
| 源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/103211]  |
| 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.Tech Univ Denmark, Dept Phys, PPFE, Bldg 309, DK-2800 Lyngby, Denmark 2.Univ Lorraine, Nancy, Meurthe Moselle, France 3.Mansoura Univ, Fac Sci, Phys Dept, Mansoura 35516, Egypt 4.Univ Carlos III Madrid, Av Univ 30, Madrid 28911, Spain 5.MIT, Plasma Sci & Fus Ctr, 77 Massachusetts Ave, Cambridge, MA 02139 USA 6.Commonwealth Fus Syst, Cambridge, MA USA 7.Dalian Univ Technol, Sch Phys & Optoelect, Dalian, Peoples R China 8.Lawrence Livermore Natl Lab, Livermore, CA 94550 USA 9.Univ Sci & Technol China, Hefei 230026, Peoples R China 10.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China |
| 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). |
入库方式： OAI收割
来源：合肥物质科学研究院
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