Empirical scaling of then=2 error field penetration threshold in tokamaks
文献类型:期刊论文
作者 | Logan, N. C.2; Park, J. -K.2; Hu, Q.2; Paz-Soldan, C.3; Markovic, T.4,5; Wang, H.6; In, Y.7; Piron, L.8,9; Piovesan, P.1; Myers, C. E.2,12 |
刊名 | NUCLEAR FUSION
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出版日期 | 2020-08-01 |
卷号 | 60 |
关键词 | locked modes error field correction tokamak ITER |
ISSN号 | 0029-5515 |
DOI | 10.1088/1741-4326/ab94f8 |
通讯作者 | Logan, N. C.(nlogan@pppl.gov) |
英文摘要 | This paper presents a multi-machine, multi-parameter scaling law for then = 2 core resonant error field threshold that leads to field penetration, locked modes, and disruptions. Here,nis the toroidal harmonic of the non-axisymmetric error field (EF). While density scalings have been reported by individual tokamaks in the past, this work performs a regression across a comprehensive range of densities, toroidal fields, and pressures accessible across three devices using a common metric to quantify the EF in each device. The metric used is the amount of overlap between an EF and the spectrum that drives the largest linear ideal MHD resonance, known as the "dominant mode overlap". This metric, which takes into account both the external field and plasma response, is scaled against experimental parameters known to be important for the inner layer physics. These scalings validate non-linear MHD simulation scalings, which are used to elucidate the dominant inner layer physics. Both experiments and simulations show that core penetration thresholds for EFs with toroidal mode numbern = 2 are of the same order as then = 1 thresholds that are considered most dangerous on current devices. Bothn = 1 andn = 2 thresholds scale to values within the ITER design tolerances, but data from additional devices with a range of sizes are needed in order to increase confidence in quantitative extrapolations ofn = 2 thresholds to ITER. |
WOS关键词 | RESONANT MAGNETIC PERTURBATIONS ; DIII-D ; FEEDBACK STABILIZATION ; MHD STABILITY ; LOCKED MODES ; PLASMA |
资助项目 | U.S. Department of Energy Office of Science Office of Fusion Energy Sciences using the DIII-D National Fusion Facility, DOE Office of Science user facilities[DE-FC02-04ER54698] ; U.S. Department of Energy Office of Science Office of Fusion Energy Sciences using the DIII-D National Fusion Facility, DOE Office of Science user facilities[DE-AC02-09CH11466] ; U.S. Department of Energy Office of Science Office of Fusion Energy Sciences using the DIII-D National Fusion Facility, DOE Office of Science user facilities[DE-FC02-99ER54512] ; U.S. Department of Energy Office of Science Office of Fusion Energy Sciences using Alcator C-Mod, DOE Office of Science user facilities[DE-FC02-04ER54698] ; U.S. Department of Energy Office of Science Office of Fusion Energy Sciences using Alcator C-Mod, DOE Office of Science user facilities[DE-AC02-09CH11466] ; U.S. Department of Energy Office of Science Office of Fusion Energy Sciences using Alcator C-Mod, DOE Office of Science user facilities[DE-FC02-99ER54512] ; National Key R&D Program of China[2017YFE0301100] ; Czech Science Foundation (GA CR)[19-15229S] ; MEYS of CR projects[8D15001] ; MEYS of CR projects[LM2015045] ; project COMPASS-U: Tokamak for cutting-edge fusion research[CZ.02.1.01/0.0/0.0/16_019/0000768] ; European structural and investment funds ; EURATOM research and training program 2014-2018[633053] ; EURATOM research and training program 2019-2020[633053] |
WOS研究方向 | Physics |
语种 | 英语 |
WOS记录号 | WOS:000553758500001 |
出版者 | IOP PUBLISHING LTD |
资助机构 | U.S. Department of Energy Office of Science Office of Fusion Energy Sciences using the DIII-D National Fusion Facility, DOE Office of Science user facilities ; U.S. Department of Energy Office of Science Office of Fusion Energy Sciences using Alcator C-Mod, DOE Office of Science user facilities ; National Key R&D Program of China ; Czech Science Foundation (GA CR) ; MEYS of CR projects ; project COMPASS-U: Tokamak for cutting-edge fusion research ; European structural and investment funds ; EURATOM research and training program 2014-2018 ; EURATOM research and training program 2019-2020 |
源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/70970] ![]() |
专题 | 中国科学院合肥物质科学研究院 |
通讯作者 | Logan, N. C. |
作者单位 | 1.Consorzio RFX, Padua, Italy 2.Princeton Plasma Phys Lab, Princeton, NJ 08540 USA 3.Gen Atom, San Diego, CA 92186 USA 4.Czech Acad Sci, Inst Plasma Phys, Prague, Czech Republic 5.Charles Univ Prague, Fac Math & Phys, Prague, Czech Republic 6.Chinese Acad Sci, Inst Plasma Phys, Beijing, Peoples R China 7.Ulsan Natl Inst Sci & Technol, Ulsan, South Korea 8.Culhan Ctr Fus Energy, Abingdon, Oxon, England 9.Culhan Ctr Fus Energy, Abingdon, North Ireland 10.Max Planck Inst Plasma Phys, Garching, Germany |
推荐引用方式 GB/T 7714 | Logan, N. C.,Park, J. -K.,Hu, Q.,et al. Empirical scaling of then=2 error field penetration threshold in tokamaks[J]. NUCLEAR FUSION,2020,60. |
APA | Logan, N. C..,Park, J. -K..,Hu, Q..,Paz-Soldan, C..,Markovic, T..,...&Munaretto, S..(2020).Empirical scaling of then=2 error field penetration threshold in tokamaks.NUCLEAR FUSION,60. |
MLA | Logan, N. C.,et al."Empirical scaling of then=2 error field penetration threshold in 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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