Results 31 to 40 of about 144 (106)

Simulation of impurity transport in the peripheral plasma due to the emission of dust in long pulse discharges on the Large Helical Device

Nuclear Materials and Energy, 2017
Two different plasma termination processes by dust emission were observed in long pulse discharges in the Large Helical Device. One is a plasma termination caused by large amounts of carbon dust released from a lower divertor region.
M. Shoji, G. Kawamura, R. Smirnov, A. Pigarov, Y. Tanaka, S. Masuzaki, Y. Uesugi   +6 more
doaj   +1 more source

Integrated modelling: Coupling of surface evolution and plasma-impurity transport

Nuclear Materials and Energy, 2020
During the interaction of the scrape off layer (SOL) plasma with the first wall the evolution of both wall and plasma are tightly coupled: The erosion of the first wall leads to an impurity concentration in the plasma which affects the particle and power
K. Schmid, F. Effenberg, A. Dinklage, L. Rudischhauser, Y. Gao, M. Mayer, S. Brezinsek, J. Geiger, G. Fuchert, V. Miklos, H. Smith, Y. Turkin, K. Rahbarnia, T. Stange, K. Ipp, J. Brunner, U. Neuner, A. Pavone, U. Hoefel, H. Ipp   +19 more
doaj   +1 more source

EMC3-Eirene simulations of the spatial dependence of the tungsten divertor retention in ASDEX Upgrade [PDF]

Plasma Physics and Controlled Fusion, 2011
The Edge Monte Carlo 3D (EMC3)-Eirene code package is applied to simulate the deuterium plasma and neutral particle as well as the tungsten impurity transport in ASDEX Upgrade. Good agreement is found for the deuterium bulk plasma for an L-mode discharge both in the upstream and downstream profiles.
Lunt, T., Feng, Y., Krieger, K., Neu, R., Müller, H. W., Wolfrum, E., Willensdorfer, M., Wischmeier, M., ASDEX Upgrade Team   +8 more
openaire   +3 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

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

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

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

Edge plasma measurements on the OP 1.2a divertor plasmas at W7-X using the combined probe

Nuclear Materials and Energy, 2019
During its second operational campaign (OP 1.2a) W7-X operated with an edge island divertor. Much higher densities (1020m−3) than in to the previous, limiter campaign were achieved.
P. Drews, C. Killer, J. Cosfeld, A. Knieps, S. Brezinsek, M. Jakubowski, C. Brandt, S. Bozhenkov, A. Dinklage, J. Cai, M. Endler, K. Hammond, M. Henkel, Y. Gao, J. Geiger, O. Grulke, D. Höschen, R. König, A. Krämer-Flecken, Y. Liang, Y. Li, S. Liu, H. Niemann, D. Nicolai, O. Neubauer, U. Neuner, M. Rack, K. Rahbarnia, L. Rudischhauser, N. Sandri, G. Satheeswaran, S. Schilling, H. Thomsen, T. Windisch, S. Sereda   +34 more
doaj   +1 more source