Results 81 to 90 of about 806 (137)

FLARE: field line analysis and reconstruction for 3D boundary plasma modeling

open access: yesNuclear Fusion
The FLARE code is a magnetic mesh generator that is integrated within a suite of tools for the analysis of the magnetic geometry in toroidal fusion devices.
H. Frerichs
doaj   +1 more source

Divertor detachment in the pre-fusion power operation phase in ITER during application of resonant magnetic perturbations [PDF]

open access: yes, 2021
Bonnin, X.   +8 more
core   +1 more source

Conditions and benefits of X-point radiation for the island divertor

open access: yesNuclear Fusion
We present a method to geometrically quantify the three magnetic island chains with the poloidal mode numbers m = 4, 5, and 6 (referred to in this paper as high-iota, standard, and low-iota islands, respectively), on which the W7-X divertor relies.
Y. Feng   +19 more
doaj   +1 more source

Improved weighted sum estimation of total radiated power at W7-X

open access: yesNuclear Fusion
As magnetic confinement devices move toward higher fusion powers, moderating the heat load to the plasma-facing components becomes increasingly challenging. Efficient power dissipation can be achieved through control of the plasma radiation.
G. Partesotti   +6 more
doaj   +1 more source

First Observation of a Stable Highly Dissipative Divertor Plasma Regime on the Wendelstein 7-X Stellarator [PDF]

open access: yes, 2019
Alonso, A.   +40 more
core   +1 more source

3-D-Modellierung des Wärmetransports in Wendelstein 7-X Startup-Plasmen mit EMC3-EIRENE

open access: yes, 2016
La topología de borde magnético de la configuración de campo de inicio del limitador Wendelstein 7-X presenta tubos de flujo magnético separados de tres longitudes de conexión de objetivo a objetivo diferentes L C. Las simulaciones se realizan con el código de Monte Carlo de transporte neutro cinético y fluido de borde de plasma 3-D EMC3-EIRENE para ...
Effenberg, Florian   +12 more
openaire   +1 more source

Taming harmful bursts and heat flux in high-confinement tokamak plasmas. [PDF]

open access: yesNat Commun
Hu QM   +31 more
europepmc   +1 more source

Modeling the toroidal asymmetry of the heat load impacted by nitrogen injection in EAST using EMC3-EIRENE [PDF]

open access: yes, 2021
Cheng, J.   +15 more
core   +2 more sources

EMC3-EIRENE コードを用いた JT-60SA 周辺プラズマモデリング

open access: yesEMC3-EIRENE コードを用いた JT-60SA 周辺プラズマモデリング
ELM 制御における外部共鳴摂動磁場(RMP)の有効性が多くの核融合実験装置で確認されたことから、原型炉を含む将来の装置への適用の検討が始まっている。新たな装置設計には計算機シミュレーションによる予測が不可欠である、3次元性を有する RMP を取り込んだ周辺プラズマシミュレーション研究は十分でない。応募者らは今年度より、近々運転の開始される JT-60SA を対象とし、3次元輸送コード EMC3-EIRENE による周辺プラズマモデリング研究を開始した。講演では、軸対称グリッドの作成と初期的な計算結果を述べ、2次元輸送コード SONIC との比較計算の進捗について発表する。将来的には、RMP を取り込んだ非軸対称グリッドでの3次元計算ならびに実験との比較 ...
openaire  

Numerical Investigation of Impurity Seeded Radiation Enhancement in the Divertor region with Magnetic Perturbations in ASDEX Upgrade [PDF]

open access: yes, 2015
ASDEX Upgrade Team, ASDEX   +11 more
core   +1 more source

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