Results 61 to 70 of about 984 (168)

Plasma edge modelling with ICRF coupling

EPJ Web of Conferences, 2017
The physics of Radio-Frequency (RF) wave heating in the Ion Cyclotron Range of Frequencies (ICRF) in the core plasmas of fusion devices are relatively well understood while those in the Scrape-Off Layer (SOL) remain still unresolved.
Zhang Wei, Coster David, Feng Yuhe, Lunt Tilmann, Aguiam Diogo, Bilato Roberto, Bobkov Volodymyr, Jacquot Jonathan, Jacquet Philippe, Lerche Ernesto, Noterdaeme Jean-Marie, Tierens Wouter   +11 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

Self‐consistent transport simulation of boron dust particle injection in the peripheral plasma in Large Helical Device

Contributions to Plasma Physics, Volume 64, Issue 7-8, August-September 2024.
Abstract The trajectories and the ablation positions of boron dust particles dropped from an impurity powder dropper in the peripheral plasma in the Large Helical Device (LHD) were calculated using a three‐dimensional edge plasma simulation code (EMC3‐EIRENE) and a dust transport simulation code (DUSTT).
M. Shoji, G. Kawamura, R. Smirnov, Y. Tanaka, S. Masuzaki, F. Nespoli, E. Gilson, R. Lunsford   +7 more
wiley   +1 more source

Boron transport simulation using the ERO2.0 code for real-time wall conditioning in the large helical device

Nuclear Materials and Energy, 2020
The three-dimensional Monte-Carlo impurity transport and plasma surface interaction code ERO2.0 is applied to a full-torus model for the Large Helical Device (LHD).
M. Shoji, G. Kawamura, J. Romazanov, A. Kirschner, A. Eksaeva, D. Borodin, S. Masuzaki, S. Brezinsek   +7 more
doaj   +1 more source

Toward plasma drifts in EMC3: Implementation of gradient, divergence, and particle tracing schemes

Contributions to Plasma Physics, Volume 64, Issue 7-8, August-September 2024.
Abstract This paper presents a first implementation of gradient, divergence, and particle tracing schemes for the EMC3 code, a stochastic 3D plasma fluid code widely employed for edge plasma and impurity transport modeling in tokamaks and stellarators.
Ruben De Wolf, Felix Reimold, Yuhe Feng, Matthieu Jacobs, Wouter Dekeyser, Giovanni Samaey, Martine Baelmans   +6 more
wiley   +1 more source

Measurements of three-dimensional flows induced by magnetic islands

Physical Review Research, 2020
Magnetic reconnection and the resulting complex magnetic field geometries are fundamental aspects of our understanding of both space and laboratory plasmas.
C. M. Samuell, J. D. Lore, W. H. Meyer, M. W. Shafer, S. L. Allen, T. E. Evans, J. Howard   +6 more
doaj   +1 more source

Analysis of the neutral fluxes in the divertor region of Wendelstein 7-X under attached and detached conditions using EMC3-EIRENE [PDF]

, 2023
Dieter Boeyaerta, Feng, Yuhe, H. Frerichs, T. Kremeyer, D. Naujoks, F. Reimold, O. Schmitz, V. Winters, S. Bozhenkov, J. Fellinger, M. Jakubowski, R. König, M. Krychowiak, V. Perseo, G. Schlisio, U. Wenzel, W -X team   +16 more
openalex   +3 more sources

EMC3-Eirene simulations of the impact of Magnetic Perturbations on the neutral particle recycling in ASDEX Upgrade

, 2013
T. Lunt, Y. Feng, E. Wolfrum, S. Potzel, S. K. Rathgeber, W. Suttrop   +5 more
openalex   +2 more sources

Full wave propagation modelling in view to integrated ICRH wave coupling/RF sheaths modelling [PDF]

, 2015
RF sheaths rectification can be the reason for operational limits for Ion Cyclotron Range of Frequencies (ICRF) heating systems via impurity production or excessive heat loads.
Bobkov, Volodymyr, Colas, Laurent, Eurofusion Mst1 Team, Asdex Upgrade Team, Heuraux, Stéphane, Jacquot, Jonathan, Křivská, Alena, Lu, Lingfeng, Noterdaeme, Jean-Marie, Supra Team, Tore   +8 more
core   +1 more source

Modeling of plasma beta effects on the island divertor transport in the standard configuration of W7-X

Nuclear Fusion, 2023
The influence of plasma beta effects on the edge plasma transport in the Wendelstein 7-X standard configuration is studied systematically by using EMC3-EIRENE combined with a 3D equilibrium code named HINT. The magnetic topology changes induced by plasma
S. Xu, Y. Liang, A. Knieps, S. Zhou, Y. Feng, D. Reiter, Y. Suzuki, M. Jia, J. Geiger, F. Reimold, R. König, A. Dinklage, D. Harting, Y. Luo, P. Drews, M. Jakubowski, Y. Gao, E. Pasch, A. Pandey, A. Langenberg, N. Pablant, S. Brezinsek, E. Wang, S. Liu, H.M. Xiang, O. Neubauer, J. Huang, J. Cai, J. Yang, J. Liu, L. Liao, Y.C. Gao, the W7-X Team   +32 more
doaj   +1 more source