Results 31 to 40 of about 806 (137)

Recent progress on improving ICRF coupling and reducing RF-specific impurities in ASDEX Upgrade [PDF]

, 2017
The recent scientific research on ASDEX Upgrade (AUG) has greatly advanced solutions to two issues of Radio Frequency (RF) heating in the Ion Cyclotron Range of Frequencies (ICRF): (a) the coupling of ICRF power to the plasma is significantly improved by
Ana Kostic, Angelo A. Tuccilo, Antonio Silva, Arne Kallenbach, Bobkov, Bobkov, Bobkov, Brambilla, David Coster, Diogo Aguiam, Dirk Van Eester, Feng, Guillermo Suárez, Helmut Faugel, Helmut Fuenfgelder, J. Hillairet, Jean-Marie Noterdaeme, Jonathan Jacquot, Kristel Crombé, Laurent Colas, Mariia Usoltceva, Onofrio Tudisco, Philippe Jacquet, Qingxi Yang, Riccardo Maggiora, Roberto Bilato, Roman Ochoukov, Tilmann Lunt, Volodymyr Bobkov, Wei Zhang, Wouter Tierens, Yongsheng Wang, Yuhe Feng, Zhang   +33 more
core   +2 more sources

Impact of impurities on the effective charge state distribution in the limiter plasmas of Wendelstein 7-X

Nuclear Materials and Energy, 2019
Carbon and oxygen have been identified as the two major impurities in the first limiter operational phase of the stellarator Wendelstein 7-X. We evaluate basic differences between these impurities regarding the effective charge state in the boundary ...
J. Cosfeld, M. Rack, D. Reiter, P. Drews, Y. Feng, D. Zhang   +5 more
doaj   +1 more source

Estimations of edge plasma and impurity performance on HL-2M with EMC3-EIRENE modelling

Physica Scripta, 2021
Abstract The three-dimensional edge transport code EMC3-EIRENE has been employed to investigate the edge plasma behavior and carbon impurity transport in the HuanLiuqi-2M (HL-2M) tokamak. It is found that the outboard divertor target has a narrower flux deposition width and therefore undergoes more intense peak ...
Z Liang, S Y Dai, Y Feng, D Z Wang
openaire   +2 more sources

Impurity transport simulation in the peripheral plasma in the large helical device with tungsten closed helical divertor

Nuclear Materials and Energy, 2018
Long pulse plasma discharges in the Large Helical Device have been often interrupted by iron dust emission induced by electric arcing on the surface of the vacuum vessel.
M. Shoji, G. Kawamura, S. Masuzaki, T. Morisaki   +3 more
doaj   +1 more source

Effect of magnetic perturbation fields on power decay length in EMC3-EIRENE simulations and comparison to experiment in ASDEX upgrade

Nuclear Materials and Energy, 2019
Previous simulation results for the tokamak ASDEX Upgrade have shown that Magnetic Perturbation (MP) fields could lead to a decrease of the peak heat flux onto the divertor targets. However, experimentally, such a decrease has not been observed.
D. Brida, T. Lunt, M. Faitsch, M. Wischmeier, Y. Feng, W. Suttrop, U. Stroth, T. Eich   +7 more
doaj   +1 more source

2D and 3D studies of the X-divertor configuration in the future upper divertor of ASDEX upgrade

Nuclear Materials and Energy, 2019
ASDEX Upgrade is planning the installation of a pair of in-vessel coils in order to study alternative divertor configurations, like an X-divertor (XD) or a Snowflake (SF) in a machine with a high heating power compared to its size.
T. Lunt, O. Pan, A. Herrmann, M. Teschke, M. Dunne, Y. Feng, M. Wischmeier   +6 more
doaj   +1 more source

EMC3-EIRENE simulation of first wall recycling fluxes in W7-X with relation to H-alpha measurements [PDF]

, 2021
In the Wendelstein 7-X stellarator, the main locations of particle sources are expected to be the carbon divertors, baffles and graphite heat shield first wall. In this paper, the heat shield is implemented in EMC3-EIRENE to understand the expected areas
Biedermann, C., Bozhenkov, S., Drewelow, P., Endler, M., Feng, Y., Frerichs, H., Fuchert, G., Gantenbein, Gerd, Gao, Y., Geiger, J., Harris, J. H., Huber, Martina, Illy, Stefan, Jakubowski, M., Jelonnek, John, Kobarg, Thorsten, Kornejew, P., Kremeyer, T., Krychowiak, M., König, R., Lang, Rouven, Leonhardt, Wolfgang, Mellein, Daniel, Niemann, H., Papenfuß, Daniel, Pasch, E., Puig-Sitjes, A., Reimold, F., Romba, T., Scherer, Theo, Schlisio, G., Scott, E. R., Thumm, Manfred, W7-X Team, Wadle, Simone, Weggen, Jörg, Winters, V. R., Wurden, G. A.   +37 more
core   +2 more sources

Investigation of 3D effects on heat fluxes in performance-optimized island divertor configurations at Wendelstein 7-X

Nuclear Materials and Energy, 2019
The 3D effects on divertor heat loads have been investigated for performance-optimized island divertor configurations at Wendelstein 7-X with 3D modeling and IR camera measurements.
F. Effenberg, H. Niemann, Y. Feng, J. Geiger, O. Schmitz, Y. Suzuki, A. Ali, T. Barbui, S. Brezinsek, H. Frerichs, M. Jakubowski, R. König, M. Krychowiak, A. Puig Sitjes, J.C. Schmitt, T. Sunn Pedersen   +15 more
doaj   +1 more source

Impacts of neon injection position and direction on toroidally asymmetric heat load distribution for EAST tokamak

Nuclear Materials and Energy, 2023
The impacts of neon injection positions and directions on the toroidally asymmetric heat load distributions on the divertor targets have been investigated for EAST tokamak by means of three-dimensional (3D) edge transport code EMC3-EIRENE. The heat loads
B. Liu, S.Y. Dai, G. Kawamura, L. Zhang, Z.S. Yang, G.J. Niu, Y. Feng, D.Z. Wang   +7 more
doaj   +1 more source

First EMC3‐EIRENE Simulations with Divertor Legs of LHD in Realistic Device Geometry

Contributions to Plasma Physics, 2014
AbstractAn extended mesh system for EMC3‐EIRENE has been developed to simulate peripheral plasma including the ergodic and the divertor leg regions of LHD. Both the open and the closed divertor configurations are available. A series of simulations for 8MW input power, five different electron densities at the LCFS (last closed flux surface) and the open/
Kawamura, G., Feng, Y., Kobayashi, M., Shoji, M., Morisaki, T., Masuzaki, S., Tomita, Y.   +6 more
openaire   +2 more sources