Results 71 to 80 of about 984 (168)

Comparison of divertor heat loads and access to detachment for n = 3 and n = 4 toroidal mode RMP scenarios in ITER

Nuclear Fusion
A comparison of partial detachment and divertor heat loads is made for n  = 3 and n  = 4 toroidal mode resonant magnetic perturbation (RMP) scenarios for ITER.
J. Van Blarcum, H. Frerichs, L. Li, Y.Q. Liu, A. Loarte, R.A. Pitts, O. Schmitz   +6 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  

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

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

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

Investigating the role of divertor geometry on density build-up in the island divertor

Nuclear Materials and Energy
The island divertor has been proposed for power and particle exhaust in stellarators. It is investigated in the Wendelstein 7-X (W7-X) experiment. The divertor capabilities such as particle exhaust or radiative power dissipation scale with the divertor ...
N. Maaziz, F. Reimold, V.R. Winters, D. Bold, Y. Feng, V. Perseo   +5 more
doaj   +1 more source

Spatially resolved measurement of helium atom emission line spectrum in scrape-off layer of Heliotron J by near-infrared Stokes spectropolarimetry. [PDF]

Sci Rep, 2022
Chatani T, Shikama T, Ueno Y, Kado S, Kawazome H, Minami T, Matoike R, Murakumo M, Kobayashi S, Ohshima S, Iwata A, Oishi T, Ishizawa A, Nakamura Y, Okada H, Konoshima S, Mizuuchi T, Nagasaki K, Hasuo M.   +18 more
europepmc   +1 more source

Conduction-based model of the Scrape-Off Layer power sharing between inner and outer divertor in diverted low-density tokamak plasmas

Nuclear Materials and Energy, 2019
A simple analytic model for the repartition of the Scrape-Off Layer (SOL) exhaust power between the inner and outer divertors in a diverted low-density tokamak plasma is introduced. Electron heat conduction is assumed to dominate the heat transport, from
R. Maurizio, B.P. Duval, B. Labit, H. Reimerdes, C. Theiler, C.K. Tsui, J. Boedo, H. De Oliveira, O. Février, U. Sheikh, M. Spolaore, K. Verhaegh, N. Vianello, M. Wensing   +13 more
doaj   +1 more source

Assessing wall heat fluxes in the quasi-continuous exhaust regime at ASDEX Upgrade

Nuclear Fusion
The 3D fluid edge code EMC3-EIRENE has been used to simulate three ASDEX Upgrade discharges with the same equilibrium but different upstream collisionality $\nu^*$ .
L. Scotti, D. Brida, M. Cavedon, A. Redl, M. Faitsch, G. Grenfell, T. Lunt, P. David, R. Fischer, the Eurofusion Tokamak Exploitation Team, the ASDEX Upgrade Team   +10 more
doaj   +1 more source

Overview of ASDEX Upgrade results [PDF]

, 2017
The ASDEX Upgrade (AUG) programme is directed towards physics input to critical elements of the ITER design and the preparation of ITER operation, as well as addressing physics issues for a future DEMO design.
ASDEX Upgrade Team, EUROfusion MST1 Team, Mantsinen, Mervi   +2 more
core   +1 more source