Results 31 to 40 of about 2,743 (148)

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

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

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

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

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

EMC3–EIRENE simulations of neon impurity seeding effects on heat flux distribution on CFETR

Nuclear Fusion, 2022
Abstract The numerical modelling of the heat flux distribution with neon impurity seeding on China fusion engineering test reactor has been performed by the three-dimensional (3D) edge transport code EMC3–EIRENE. The maximum heat flux on divertor targets is about 18 MW m−2 without impurity seeding under the input power of 200 MW entering
S.Y. Dai, D.F. Kong, V.S. Chan, L. Wang, Y. Feng, D.Z. Wang   +5 more
openaire   +2 more sources

A neural network-based method for input parameter optimization of edge transport modeling utilizing experimental diagnostics

Nuclear Fusion
A neural network-based method is developed to fast optimize EMC3-EIRENE input parameters, enabling EMC3-EIRENE to produce synthetic data that closely match experimental measurements on Wendelstein 7-X.
Y. Luo, S. Xu, Y. Liang, E. Wang, J. Cai, Y. Feng, D. Reiter, A. Knieps, S. Brezinsek, D. Harting, M. Krychowiak, D. Gradic, P. Ren, D. Zhang, Y. Gao, G. Fuchert, A. Pandey, M. Jakubowski, the W7-X Team   +18 more
doaj   +1 more source