Results 61 to 70 of about 806 (137)

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

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

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

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

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

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

Heat flux mitigation characteristics in the radiative divertors with multi-peaks of heat flux in the large helical device [PDF]

ORCID　0000-0001-6090-5010In this study, the effects of impurity seeding on the one- and two-dimensional heat flux profiles of the large helical device divertor with a multi-peaks of heat flux were investigated, focusing on the heat-flux-reduction ...
123133, 123964, 127219, 66267, 66269, 66274, 66765, HAYASHI, Yuki, KAWAMURA, Gakushi, KOBAYASHI, Masahiro, MASUZAKI, Suguru, MUKAI, Kiyofumi, MURASE, Takanori, TANAKA, Hirohiko   +13 more
core   +1 more source

Correlation between radiated power and target heat flux in the island divertor of W7-X

Nuclear Fusion
Radiative losses from the plasma represent a key component of global power balance in a magnetic confinement fusion device. Measurements of the plasma radiation and its spatial distribution are essential for physical studies and to ensure safe machine ...
G. Partesotti, F. Reimold, G.A. Wurden, N. Maaziz, A. Tsikouras, B.J. Peterson, F. Federici, K.A. Siever, A. Puig Sitjes, M. Jakubowski, Y. Gao, T. Nishizawa, K. Mukai, the W7-X Team   +13 more
doaj   +1 more source

Simulations of gas puff effects on edge density and ICRF coupling in ASDEX upgrade using EMC3-Eirene [PDF]

, 2015
ASDEX Upgrade Team, ASDEX, Bobkov, V., Brida, D., Coster, D., Feng, Y., Jaquet, P., Lunt, T., Noterdaeme, Jean-Marie, Zhang, Wei   +8 more
core   +1 more source