Results 11 to 20 of about 984 (168)

Impact of spatially varying transport coefficients in EMC3-Eirene simulations of W7-X and assessment of drifts [PDF]

Nuclear Fusion
Modelling the scrape-off layer of a stellarator is challenging due to the complex magnetic 3D geometry. The here presented study analyses simulations of the scrape-off layer (SOL) of the stellarator Wendelstein 7-X (W7-X) using spatially varying ...
David Bold, Felix Reimold, Holger Niemann, Yu Gao, Marcin Jakubowski, Carsten Killer, Victoria R. Winters, Nassim Maaziz, the W7-X Team   +8 more
doaj   +9 more sources

Numerical accuracy and convergence with EMC3-EIRENE [PDF]

Plasma Science and Technology, 2019
The iterative Monte Carlo (MC) code EMC3-EIRENE is frequently used for plasma edge simulations in 3D applications. So far, a quantitative evaluation of the numerical quality of the code results remains an open issue. In this paper, we demonstrate a framework for the practical assessment of accuracy and convergence with EMC3-EIRENE. Moreover, we provide
Kristel Ghoos, H. Frerichs, W. Dekeyser, Giovanni Samaey, Martine Baelmans   +4 more
openalex   +3 more sources

First Application of 3D Peripheral Plasma Transport Code EMC3-EIRENE to Heliotron J

Plasma and Fusion Research, 2019
R Matoike, G Kawamura, S Ohshima
exaly   +5 more sources

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   +2 more sources

TCV divertor upgrade for alternative magnetic configurations [PDF]

Nuclear Materials and Energy, 2017
The Swiss Plasma Center (SPC) is planning a divertor upgrade for the TCV tokamak. The upgrade aims at extending the research of conventional and alternative divertor configurations to operational scenarios and divertor regimes of greater relevance for a ...
H. Reimerdes, S. Alberti, P. Blanchard, P. Bruzzone, R. Chavan, S. Coda, B.P. Duval, A. Fasoli, B. Labit, B. Lipschultz, T. Lunt, Y. Martin, J.-M. Moret, U. Sheikh, B. Sudki, D. Testa, C. Theiler, M. Toussaint, D. Uglietti, N. Vianello, M. Wischmeier   +20 more
doaj   +7 more sources

First EMC3-Eirene simulations of the TCV snowflake divertor [PDF]

Plasma Physics and Controlled Fusion, 2014
One of the approaches to solve the heat load problem in a divertor tokamak is the so called 'snowflake' (SF) configuration, a magnetic equilibrium with two nearby x-points and two additional divertor legs. Here we report on the first EMC3-Eirene simulations of plasma-and neutral particle transport in the scrape-off layer of a series of TCV SF ...
T. Lunt, G. P. Canal, Y. Feng, H. Reimerdes, B.P. Duval, B. Labit, W.A.J. Vijvers, D. Coster, K. Lackner, M. Wischmeier   +9 more
openalex   +3 more sources

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   +3 more sources

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

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   +3 more sources

Transport simulations of linear plasma generators with the B2.5-Eirene and EMC3-Eirene codes

Journal of Nuclear Materials, 2014
Linear plasma generators are cost effective facilities to simulate divertor plasma conditions of present and future fusion reactors. The codes B2.5-Eirene and EMC3-Eirene were extensively used for design studies of the planned Material Plasma Exposure eXperiment (MPEX).
J. Rapp, L.W. Owen, X. Bonnin, J. F. Caneses, J.M. Canik, Cormac Corr, J. Lore   +6 more
openalex   +5 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
Shuyu Dai, Defeng Kong, V. S. Chan, Liang Wang, Y. Feng, Dezhen Wang   +5 more
openalex   +3 more sources