Results 51 to 60 of about 984 (168)

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

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

The developement of Findif code + first EMC3-Eirene comparison

, 2019
Stellarator plasma edge modelling Introduction (machine, code) Transport model Local magnetic coordinates Wendelstein-7X vacuum field structure Mesh generation procedure Numerical approach Temperatures, density and velocity ...
Pełka, Grzegorz, Effenberg, Florian, Stępniewski, Wlodzimierz, Zagórski, Roman   +3 more
openaire   +1 more source

Integrated modelling of lithium transport and radiation under a liquid lithium divertor on EAST

Nuclear Materials and Energy
The edge transport and core accumulation of lithium (Li) impurity under a liquid Li divertor on EAST have been investigated by the EMC3-EIRENE and STRAHL codes, respectively.
Z.X. Wen, Z.H. Gao, B. Liu, Z. Zhou, Z.C. Lin, Y. Feng, S.Y. Dai   +6 more
doaj   +1 more source

3D modeling of boron transport in DIII-D L-mode wall conditioning experiments

Nuclear Materials and Energy, 2021
DIII-D L-mode experiments with local boron powder injection for real-time wall conditioning have been interpreted for the first time with the 3D plasma edge transport Monte Carlo code EMC3-EIRENE.
F. Effenberg, A. Bortolon, H. Frerichs, B. Grierson, J.D. Lore, T. Abrams, T.E. Evans, Y. Feng, R. Lunsford, R. Maingi, A. Nagy, R. Nazikian, D. Orlov, J. Ren, D.L. Rudakov, W.R. Wampler, H.Q. Wang   +16 more
doaj   +1 more source

First EMC3-Eirene simulations of the impact of the edge magnetic perturbations at ASDEX Upgrade compared with the experiment

, 2012
Bernert, M., de Marne, P., Feng, Y., Herrmann, A., Lunt, T., McDermott, R., Müller, H., Potzel, S., Pütterich, T., Rathgeber, S., Suttrop, W., Viezzer, E., Wilensdorfer, M., Wolfrum, E.   +13 more
core   +3 more sources

Validation of the plasma-wall interaction simulation code ERO2.0 by the analysis of tungsten migration in the open divertor region in the Large Helical Device

Nuclear Materials and Energy, 2022
Tungsten migration in the open divertor region in the Large Helical Device is analyzed for validating the three-dimensional plasma-wall interaction simulation code ERO2.0.
M. Shoji, G. Kawamura, J. Romazanov, A. Kirschner, S. Masuzaki, M. Tokitani, S. Brezinsek   +6 more
doaj   +1 more source

Heat Load Mitigation Studies in the W7‐X Stellarator Experiment

Contributions to Plasma Physics, EarlyView.
ABSTRACT During the experiments at the stellarator Wendelstein 7‐X (W7‐X) with fully water‐cooled plasma‐facing components (PFC), including carbon‐fiber composite (CFC) divertor targets with a thermal load capability of 10 MW/m2, high performance was achieved.
Dirk Naujoks, Amit Kharwandikar, Jasper Dettmar, Michael Endler, Joris Fellinger, Yu Gao, Joachim Geiger, Marcin Jakubowski, Thomas Sieber, Sebastian Thiede, Christian Voß, W7‐X Team   +11 more
wiley   +1 more source

Neural network-based surrogate model for 3D edge-plasma transport in the standard configuration of W7-X

Nuclear Fusion
This paper presents a neural‐network surrogate model for Wendelstein 7-X (W7-X) edge transport simulations, trained on an EMC3-EIRENE dataset that spans nearly the entire operating-parameter space currently explored in the W7-X standard configuration ...
Y. Luo, S. Xu, Y. Liang, E. Wang, J. Cai, A. Knieps, R. Pei, M. Tan, Y. Feng, D. Reiter, S. Brezinsek, D. Harting, M. Krychowiak, D. Gradic, M. Jakubowski, the W7-X Team   +15 more
doaj   +1 more source