Results 51 to 60 of about 806 (137)

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

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

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

Towards improved neutral exhaust in the HSX stellarator

Nuclear Materials and Energy
To improve our knowledge of neutral exhaust in non-resonant divertors, a particle exhaust study is performed for the Helically Symmetric eXperiment (HSX).
Dieter Boeyaert, Kelly A. Garcia, Heinke Frerichs, Michael J. Gerard, Aaron Bader, Robert Davies, Benedikt Geiger, John Schmitt, Oliver Schmitz   +8 more
doaj   +1 more source

大型ヘリカル装置計画から [PDF]

, 2011
大型ヘリカル装置（LHD）実験の最近の成果を中心に紹介するとともに，原点からの経緯を振り返り，将来の展望について述べる．また，共同研究を骨子とした実験体制と国際的・学際的連携についても触れる．LHD実験では本体・加熱などのハードウェアの整備とプラズマ物理学上の発見が相乗的に研究を加速している．プラズマ性能を向上させる内部拡散障壁，高イオン温度をもたらす改善モードなどの発見，非局所輸送，共鳴摂動磁場への多様なプラズマの応答などに新しい知見が開かれてきている．精密な計測機器の整備によって ...
山田 弘司
core  

Analysis of the impurity flow velocity in a wide plasma parameter range for deuterium and hydrogen plasmas in the divertor legs of the stochastic layer in LHD

Nuclear Materials and Energy, 2018
Impurity flow velocity measurements have been conducted for different magnetic field configurations in a wide plasma parameter range in the divertor leg region of LHD for understanding of the edge impurity transport.
A. Kuzmin, M. Kobayashi, T. Nakano, G. Kawamura, M. Hasuo, K. Fujii, T. Morisaki   +6 more
doaj   +1 more source

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

Journal of Nuclear Materials, 2015
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).
Rapp, J., Owen, L.W., Bonnin, X., Caneses, Juan, Canik, J, Corr, Cormac, Lore, J.D.   +6 more
openaire   +3 more sources

First experimental confirmation of island SOL geometry effects in a high radiation regime on W7-X

Nuclear Fusion
This work characterizes the detachment behavior and radiation characteristics of the low iota configuration in the Wendelstein 7-X (W7-X) stellarator. The island scrape-off layer (SOL) of the low iota has a poloidal mode number of six islands surrounding
V.R. Winters, F. Reimold, Y. Feng, D. Zhang, V. Perseo, E.R. Flom, F. Henke, D.M. Kriete, N. Maaziz, G. Partesotti, M. Jakubowski, R. König, M. Krychowiak, K.J. Brunner, J. Knauer, K. Rahbarnia, the W7-X Team   +16 more
doaj   +1 more source