Results 11 to 20 of about 1,936 (209)

Edge and core impurity behavior and transport in EAST H-mode plasma with internal transport barrier

Nuclear Fusion
After installation of tungsten divertor in EAST, impurity accumulation of tungsten ions has been frequently observed in H-mode discharge with internal transport barrier (ITB) due to an enhancement of the impurity confinement inside the ITB.
Wenmin Zhang, Ling Zhang, Yuqi Chu, Shigeru Morita, Xiang Gao, Gongshun Li, Shouxin Wang, Yunxin Cheng, Yingying Li, Ailan Hu, Chengxi Zhou, Darío Mitnik, Zhen Zhou, Hailin Zhao, Qing Zang, Ning Yan, Jihui Chen, Yinxian Jie, Jinping Qian, Haiqing Liu, Guosheng Xu, Jiansheng Hu, Yuntao Song   +22 more
doaj   +2 more sources

Controlling impurity transport in 5D gyrokinetic simulations using a transport barrier

Nuclear Fusion
The effects of transport barriers on impurity transport, specifically helium (He) and tungsten (W), are investigated using the global, flux-driven, full-F, 5D gyrokinetic code GYSELA.
G. Lo-Cascio, E. Gravier, M. Lesur, T. Réveillé, Y. Sarazin, X. Garbet, K. Lim, T. Rouyer, A. Guillevic   +8 more
doaj   +2 more sources

Turbulent drifts of impurity ions as an explanation for anomalous radial transport in the far-SOL of DIII-D

Nuclear Fusion
Successful fusion reactor operation relies on minimal core contamination by impurities, otherwise too much power may be radiated and harm performance. This requires reliable predictions of impurity transport from the scrape-off layer (SOL) into the core,
S.A. Zamperini, T.N. Bernard, D.L Rudakov, J.A Boedo   +3 more
doaj   +2 more sources

Control of tungsten impurity source and edge transport using different gas injection with full tungsten divertor on EAST

Nuclear Materials and Energy, 2022
Tungsten (W) erosion and edge transport are investigated for EAST L-mode discharges with different gas injection. It is found that W erosion can be suppressed or mitigated by Ne or D2 seeding when divertor detachment is achieved.
R. Ding, G.L. Xu, H. Wang, F. Ding, L. Zhang, Q. Zhang, K.D. Li, J.B. Liu, S. Brezinsek, A. Kirschner, S.X. Wang, B.F. Gao, L.Y. Meng, L. Wang, H. Xie, H. Si, R. Yan, D.H. Zhu, J.L. Chen   +18 more
doaj   +3 more sources

Comparison of kinetic and fluid models for tungsten impurity transport using IMPGYRO and SOLPS [PDF]

Journal of Nuclear Materials, 2013
Abstract A benchmark calculation of tungsten impurity transport comparing kinetic modeling with IMPGYRO and multi-fluid modeling with SOLPS has been performed. The primary source of tungsten has been set at the outer mid-plane in the calculations. In both cases, impurity densities are relatively large in the SOL region near the top of the machine ...
M Toma, X Bonnin, Y Homma
exaly   +4 more sources

Comparative Analysis of Impurity Transport in the Peripheral Plasma in the Large Helical Device for Carbon and Tungsten Divertor Configurations with EMC3-EIRENE

Plasma and Fusion Research, 2019
0000-0003-0655-7347Impurity transport in the peripheral plasma in the Large Helical Device for carbon and tungsten divertor configurations is analyzed using a three-dimensional edge plasma simulation code (EMC3-EIRENE).
M Shoji, G Kawamura
exaly   +6 more sources

Tungsten impurity transport experiments in Alcator C-Mod to address high priority research and development for ITERa) [PDF]

Physics of Plasmas, 2015
Experiments in Alcator C-Mod tokamak plasmas in the Enhanced D-alpha H-mode regime with ITER-like mid-radius plasma density peaking and Ion Cyclotron Resonant heating, in which tungsten is introduced by the laser blow-off technique, have demonstrated that accumulation of tungsten in the central region of the plasma does not take place in these ...
Loarte, A., Reinke, M. L., Polevoi, A. R., Hosokawa, M., Köchl, F., Pütterich, T., Dux, R., Zhogolev, V. E., Chilenski, Mark Alan, Howard, Nathaniel Thomas, Hubbard, Amanda E, Hughes Jr, Jerry, Walk Jr, John R, Rice, John E.   +13 more
openaire   +4 more sources

OEDGE modeling for the planned tungsten ring experiment on DIII-D

Nuclear Materials and Energy, 2017
The OEDGE code is used to model tungsten erosion and transport for experiments with toroidal rings of high-Z metal tiles in the DIII-D tokamak. Such modeling is needed for both experimental and diagnostic design to have estimates of the expected core and
J.D. Elder, P.C. Stangeby, T. Abrams, R. Ding, A.W. Leonard, A.G. McLean, D.L. Rudakov, E.A. Unterberg, J.G. Watkins   +8 more
doaj   +2 more sources

The effect of metastable atomic levels in neutral tungsten for erosion and impurity transport applications

Plasma Physics and Controlled Fusion, 2020
Abstract Long-lived metastable states in neutral tungsten are shown to potentially impact measurements of tungsten erosion from plasma facing components. Time-dependent collisional radiative modeling of neutral tungsten is used to analyze the role of these states in tungsten emission and ionization. The large number of non-quasistatic
C A Johnson, S D Loch, D A Ennis
exaly   +3 more sources

Modeling of tungsten impurity transport and distribution in EAST based on multi-fluid and kinetic Monte Carlo simulations

AIP Advances
In recent years, the materials of plasma facing components, such as divertor target plates, domes, and outer walls of tokamaks, such as ASDEX Upgrade, WEST, JET, EAST, and ITER, have been changed from carbon to tungsten because of its lower erosion and ...
Ziyang Wen, YiPing Chen, Ling Zhang
doaj   +2 more sources