Results 1 to 10 of about 144 (106)

TCV divertor upgrade for alternative magnetic configurations

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   +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

Study of radial field dependent flows in inboard limited Aditya-U plasmas using EMC3-Eirene simulations

Nuclear Fusion
The intrinsically generated plasma rotation in magnetically confined tokamak plasmas has implications for a number of edge and core phenomena. In recent Aditya-U tokamak circular plasma discharges with plasma current of range (142–170) kA, the toroidal ...
Arzoo Malwal, Devendra Sharma, Bibhu Prasad Sahoo, Yühe Feng   +3 more
doaj   +1 more source

Numerical modeling of impurity powder injection in W7-X

Nuclear Materials and Energy
In this work, we present numerical simulation results of powder injection in W7-X using the EMC3-EIRENE and DIS codes. First, we model powder injection experiments performed in W7-X with the Probe Mounted Powder Injector.
F. Nespoli, Y. Feng, G. Kawamura, M. Shoji, R. Lunsford, D. Hathiramani, J. Koopmann, A. Nagy, F. Effenberg, N.A. Pablant, C. Killer, D. Zhang, M. Kubkowska, S. Jablonski, G. Kocsis, B. Buttenschön, D. Nicolai   +16 more
doaj   +1 more source

Impurity leakage mechanisms in the Wendelstein 7-X island divertor under friction-dominated conditions

Nuclear Fusion
The EMC3-Eirene code was used to study the main impurity leakage mechanism for the island divertor in the standard magnetic field configuration. It was found that under experimentally accessible plasma scenarios in the last experimental campaign, the ...
V.R. Winters, F. Reimold, Y. Feng, V. Perseo, M. Beurskens, S. Bozhenkov, K.J. Brunner, G. Fuchert, R. Koenig, J. Knauer, M. Krychowiak, E. Pasch, E. Scott, D. Zhang, the W7-X Team   +14 more
doaj   +1 more source

A universal target plate design scheme for stellarators: theoretical basis and its application to heat load control

Nuclear Fusion
This study introduces a novel divertor target design scheme for stellarators, grounded in mathematical treatments and tailored to control of toroidal heat load distributions.
B. Liu, G. Kawamura, S.Y. Dai, Y. Xu, Y. Suzuki, A. Shimizu, H. Frerichs, Y. Feng   +7 more
doaj   +1 more source