Results 11 to 20 of about 112,088 (330)

Review of magnetic islands from the divertor perspective and a simplified heat transport model for the island divertor

Plasma Physics and Controlled Fusion, 2022
Magnetic islands in toroidal confinement devices are reviewed from the viewpoint of their divertor potential. Divertor-relevant geometric parameters are derived analytically, and the relationships among them are revealed.
Y. Feng
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Real-time feedback control of the impurity emission front in tokamak divertor plasmas

Nature Communications, 2021
In magnetic confinement thermonuclear fusion the exhaust of heat and particles from the core remains a major challenge. Heat and particles leaving the core are transported via open magnetic field lines to a region of the reactor wall, called the divertor.
T. Ravensbergen, M. van Berkel, A. Perek, C. Galperti, B. Duval, O. Février, R. V. van Kampen, F. Felici, J. Lammers, C. Theiler, J. Schoukens, B. Linehan, M. Komm, S. Henderson, D. Brida, M. D. de Baar   +15 more
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The effect of impurity seeding into the closed divertor on plasma detachment in the HL-2A tokamak

Nuclear Fusion, 2023
Recent progress towards an increased understanding of detached divertor physics has been made with the highly closed divertor geometry in HL-2A. Non-intrinsic impurities were injected into the outer divertor chamber, and increased divertor neutral ...
J.M. Gao, L.Z. Cai, C.Z. Cao, H.C. Ma, R. Ke, N. Wu, Y. Hu, X.Y. Gao, C.H. Cui, Z.H. Huang, L. Nie, L. Liu, Z.C. Yang, X. Yu, Y.G. Li, M. Jiang, G.Q. Xue, W.L. Zhong, T. Wu, Z.B. Shi, L.W. Yan, X.Q. Ji, M. Xu, HL-2A Team   +23 more
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Understanding detachment of the W7-X island divertor

Nuclear Fusion, 2021
The fundamental behavior of the W7-X island divertor under detached conditions, which has been theoretically predicted with the EMC3-Eirene code, is re-examined here under the experimental conditions achieved so far and compared with the first ...
Y. Feng, M. Jakubowski, R. König, M. Krychowiak, M. Otte, F. Reimold, D. Reiter, O. Schmitz, D. Zhang, C. Beidler, C. Biedermann, S. Bozhenkov, K. Brunner, A. Dinklage, P. Drewelow, F. Effenberg, M. Endler, G. Fuchert, Y. Gao, J. Geiger, K. Hammond, P. Helander, C. Killer, J. Knauer, T. Kremeyer, E. Pasch, L. Rudischhauser, G. Schlisio, T. Sunn Pedersen, U. Wenzel, V. Winters, W7-X team   +31 more
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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
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Physics design of new lower tungsten divertor for long-pulse high-power operations in EAST

, 2021
A new lower tungsten divertor has been developed and installed in the EAST superconducting tokamak to replace the previous graphite divertor with power handling capability increasing from
G.S. Xu, L. Wang, D. Yao, G. Jia, C. Sang, X.J. Liu, Y.P. Chen, H. Si, Z.S. Yang, H. Guo, H. Du, Z. Luo, H. Li, Z.B. Zhou, L. Cao, H.C. Xu, T. Xu, Z.L. Wang, P. Zi, L. Li, L. Han, J.C. Xu, J. Liu, K.D. Li, B. Cao, Y.W. Yu, F. Ding, R. Ding, N. Yan, L. Meng, Y. Tao, H.Q. Wang, Y. Zhang, L. Shao, X. Zhang, S. Zhu, B. Wan, the EAST team   +37 more
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An innovative approach to the improved radiating divertor concept by supersonic molecular beam injection on HL-2A

Nuclear Fusion, 2023
The ‘puff-and-pump’ radiating divertor condition is a promising approach for the reduction of excessive thermal power loading on the divertor targets. The divertor supersonic molecular beam injection (SMBI) system installed on HL-2A strongly enhances the
G.L. Xiao, H.L. Du, D.M. Fan, W.L. Zhong, L. Xue, C.Y. Chen, J. Yin, Y.R. Zhu, B.B. Feng, J.M. Gao, Z.H. Huang, M. Jiang, J.X. Li, A.S. Liang, R.H. Tong, N. Wu, T. Wu, Z.C. Yang, X. Yu, Y.Y. Zhong   +19 more
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Measurements of heat flux components due to charged and non-charged particles in DIII-D divertor near and under detachment

Nuclear Materials and Energy, 2023
Surfacing Eroding Thermocouples (SETC) have been used to provide high spatial and temporal resolution heat flux measurement in DIII-D. SETCs were first tested in the lower divertor of DIII-D using the Divertor Material Evaluation System (DiMES), then an ...
J. Ren, D.C. Donovan, J.G. Watkins, H.Q. Wang, X.X. Ma, R. Maurizio, M.W. Shafer, D. Rudakov, P.C. Stangeby, D. Thomas, S. Hong   +10 more
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Initial TCV operation with a baffled divertor

, 2021
The Tokamak à Configuration Variable (TCV) tokamak is in the midst of an upgrade to further its capability to investigate conventional and alternative divertor configurations. To that end, modular and removable gas baffles have been installed to decrease
H. Reimerdes, B. Duval, H. Elaian, A. Fasoli, O. Février, C. Theiler, F. Bagnato, M. Baquero-Ruiz, P. Blanchard, D. Brida, C. Colandrea, H. de Oliveira, D. Galassi, S. Gorno, S. Henderson, M. Komm, B. Linehan, L. Martinelli, R. Maurizio, J. Moret, A. Perek, H. Raj, U. Sheikh, D. Testa, M. Toussaint, C. Tsui, M. Wensing, the TCV team, the EUROfusion MST1 team, C. Tsironis   +29 more
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Design and physics basis for the upcoming DIII-D SAS-VW campaign to quantify tungsten leakage and transport in a new slot divertor geometry

Physica Scripta, 2021
A set of experiments are planned to exploit the high SOL collisionality enabled by a tightly baffled slot divertor geometry to suppress tungsten leakage in DIII-D.
T. Abrams, G. Sinclair, J. Nichols, E. Unterberg, David Donovan, J. Duran, J. Elder, F. Glass, B. Grierson, Houyang Y Guo, T. Hall, Xinxing Ma, R. Maurizio, Adam G McLean, C. Murphy, R. Nguyen, D. Rudakov, P. Stangeby, D. Thomas, S. Zamperini   +19 more
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