Results 41 to 50 of about 144 (106)

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 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

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

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

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

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

Implementation of the E×B and Grad‐B Drift in the EMC3 Code and Verification Using the Method of Manufactured Solutions

Contributions to Plasma Physics, EarlyView.
ABSTRACT Effective management of particle and power exhaust is essential for fusion reactor operation, requiring accurate 3D modeling of divertor physics. The EMC3 code is a well‐established Monte Carlo tool for plasma transport in stellarator edge regions, but until now lacked E×B$$ E\times B $$ and diamagnetic drifts.
Ruben De Wolf, Felix Reimold, Wouter Dekeyser, Yuhe Feng, Giovanni Samaey, Martine Baelmans   +5 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