Knowledge Management System of Hefei Institute of Physical Science,CAS
RF wave coupling, plasma heating and characterization of induced plasma-material interactions in WEST L-mode discharges | |
Urbanczyk, G.1; Colas, L.2; Hillairet, J.2; Lerche, E.3; Fedorczak, N.2; Morales, J.2; Gunn, J.2; Ostuni, V.2; Heuraux, S.4; Vezinet, D.2; Bobkov, V.5; Desgranges, C.2; Ekedahl, A.2; Mollard, P.2; Lombard, G.2; Pegourie, B.2; Loarer, T.2; Helou, W.6; Klepper, C. C.7; Unterberg, E. A.7; Usoltceva, M.5; Devynck, P.2; Yan, C.2; Li, J. G.8; Wang, K.1 | |
2021-08-01 | |
发表期刊 | NUCLEAR FUSION |
ISSN | 0029-5515 |
通讯作者 | Urbanczyk, G.(guiguiurban@hotmail.com) |
摘要 | Plasma heating in the full tungsten (W) environment in a steady-state tokamak (WEST) relies on electromagnetic waves in both the lower hybrid (LH) and ion cyclotron range of frequencies (ICRF). The present study focuses mostly on the optimization of discharges heated with ICRF, by reporting different methods to first optimize wave coupling, optimize their absorption and reduce the impurity production. It is shown that ICRF coupling can be optimized by moving the plasma closer to antennas, increasing the plasma density, wave frequency and LH power. We show that the absorption efficiency correlates with the hydrogen concentration with the existence of an optimum between 7% and 10% as expected for a minority heating scenario. Absolutely calibrated visible spectroscopy sightlines were used to monitor ion fluxes in different locations as part of an effort to quantitatively estimate the contribution of different impurity sources to the core contamination by tungsten. It is typically found that in discharges with high total RF-power (above 5 MW of LH and 3 MW of ICRF), divertor and antenna limiter sources can reach a similar order of magnitude during the ICRF phase. |
关键词 | ICRH WEST plasma surface interaction SOL impurity sources tungsten |
DOI | 10.1088/1741-4326/ac0d11 |
关键词[WOS] | SCRAPE-OFF LAYER ; ICRF ; TOKAMAK ; DESIGN ; WALL |
收录类别 | SCI |
语种 | 英语 |
资助项目 | Euratom research and training programme[633053] |
项目资助者 | Euratom research and training programme |
WOS研究方向 | Physics |
WOS类目 | Physics, Fluids & Plasmas |
WOS记录号 | WOS:000674463500001 |
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/334002/123252 |
专题 | 中国科学院合肥物质科学研究院 |
通讯作者 | Urbanczyk, G. |
作者单位 | 1.Shenzhen Univ, Coll Phys & Optoelect Engn, Key Lab Optoelect Devices & Syst, Shenzhen 518060, Peoples R China 2.CEA, IRFM, F-13108 St Paul Les Durance, France 3.Assoc EURATOM Belgian State, Lab Plasmafys, Trilateral Euregio Cluster, Lab Phys Plasmas, 30 Ave Renaissance, B-1000 Brussels, Belgium 4.Univ Lorraine CNRS, Inst Jean Lamour, F-54000 Nancy, France 5.Max Planck Inst Plasma Phys, Boltzmannstr 2, D-85748 Garching, Germany 6.ITER Org, Route Vinon Sur Verdon,CS 90 046, F-13067 St Paul, Lez Durance, France 7.Oak Ridge Natl Lab, Oak Ridge, TN USA 8.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China |
推荐引用方式 GB/T 7714 | Urbanczyk, G.,Colas, L.,Hillairet, J.,et al. RF wave coupling, plasma heating and characterization of induced plasma-material interactions in WEST L-mode discharges[J]. NUCLEAR FUSION,2021,61. |
APA | Urbanczyk, G..,Colas, L..,Hillairet, J..,Lerche, E..,Fedorczak, N..,...&Wang, K..(2021).RF wave coupling, plasma heating and characterization of induced plasma-material interactions in WEST L-mode discharges.NUCLEAR FUSION,61. |
MLA | Urbanczyk, G.,et al."RF wave coupling, plasma heating and characterization of induced plasma-material interactions in WEST L-mode discharges".NUCLEAR FUSION 61(2021). |
条目包含的文件 | 条目无相关文件。 |
除非特别说明,本系统中所有内容都受版权保护,并保留所有权利。
修改评论