Results 21 to 30 of about 1,936 (209)

Effect of toroidal rotation on impurity transport in tokamak improved confinement

Nuclear Fusion
The centrifugal force effects from toroidal rotation in improved confinement plasmas are analyzed on high- Z impurities in tokamaks. Tungsten (W) transport simulations are performed using the impurity transport code developed in the integrated code TASK.
Shota Mochinaga, Naohiro Kasuya, Atsushi Fukuyama, Masatoshi Yagi   +3 more
doaj   +2 more sources

Interpretive modeling of tungsten divertor leakage during experiments with neon gas seeding

Nuclear Fusion
Many existing and future tokamaks with tungsten divertors operate, or will operate, with low- Z impurity seeding, but the direct effect of these seeded impurities on tungsten Scrape-off-Layer (SOL) transport has not been explored in detail.
Matthew S. Parsons, Gregory Sinclair, Tyler Abrams, Patrick Byrne, Colin Chrystal, Florian Effenberg, Jeffrey L. Herfindal, Tomas Odstrcil, Robert S. Wilcox   +8 more
doaj   +2 more sources

Integrated modeling of RF-induced tungsten erosion at ICRH antenna structures in the WEST tokamak

Nuclear Fusion
This paper introduces STRIPE (Simulated Transport of RF Impurity Production and Emission), an advanced modeling framework developed to analyze material erosion and the global transport of eroded impurities originating from radio-frequency (RF) antenna ...
A. Kumar, W. Tierens, T. Younkin, C. Johnson, C. Klepper, A. Diaw, J. Lore, A. Grosjean, G. Urbanczyk, J. Hillairet, P. Tamain, L. Colas, C. Guillemaut, D. Curreli, S. Shiraiwa, N. Bertelli, the WEST Team   +16 more
doaj   +2 more sources

Impurity transport and its modification by MHD in tokamak plasmas, with application to Tungsten in the WEST tokamak

, 2019
The neoclassical transport of impurities is investigated analytically and numerically in this work, and the effect of a magnetic island for a WEST plasma is described. It is shown that the poloidal asymmetry of the impurity density can be described with a simple analytical model, and numerical simulations with a non linear fluid code confirm the ...
Maget, P., Frank, J, Agullo, O., Garbet, X., Lütjens, H.   +4 more
openaire   +2 more sources

Impact of E× B drift on tungsten impurity transport and analysis of its instantaneous response: a particle Monte Carlo simulation

Nuclear Fusion
Tungsten (W), as the primary plasma-facing material in tokamaks, is incompatible with the core plasma. Even extremely low concentrations of W impurities can contaminate the plasma.
Yihan Wu, Chaofeng Sang, Yilin Wang, Chen Zhang, Qingrui Zhou, Yudie He, Dezhen Wang   +6 more
doaj   +2 more sources

Impurity transport and its modification by MHD in tokamak plasmas, with application to tungsten in WEST

, 2019
Neoclassical impurity transport & poloidal asymmetry-Can be determined analytically in a self-consistent way-Natural asymmetry (no torque) has already a large impact A magnetic island suppresses thermal screening above a critical size-Verified numerically on a typical WEST plasma equilibrium-When impurity transport is predominantly turbulent (as on ...
Maget, P., Frank, J, Agullo, O., Garbet, X., Lütjens, H.   +4 more
openaire   +2 more sources

Global modelling of tungsten impurity transport based on the drift-kinetic equation, Nuclear Fusion

Global modelling of tungsten impurity transport based on the drift-kinetic equation, Nuclear Fusion
0000-0002-1642-1235 A global kinetic simulation model of collisional impurity transport is developed for evaluating the radial particle flux of tungsten impurity in the edge region of a tokamak plasma. Here, the plasma including the impurity and the background ion is presupposed to be quasi-steady.
Hoshino, Kazuo, Hatayama, Akiyoshi, NUNAMI, Masanori, HOMMA, Yuki, KANNO, Ryutaro, KAWAMURA, Gakushi   +5 more
openaire   +1 more source

DIVIMP modeling of tungsten impurity transport in ITER [PDF]

Journal of Nuclear Materials, 2007
This paper presents a modeling study of the W erosion and plasma accumulation in ITER for different levels of first wall W coverage and plasma configurations using the Monte Carlo impurity transport code DIVIMP. Based on the ion fluxes from the background plasma solutions from B2/EIRENE the W erosion is calculated by taking into account both D and ...
Schmid, K., Krieger, K., Kukushkin, A., Loarte, A.   +3 more
openaire   +3 more sources

Tungsten erosion and divertor leakage from the DIII-D SAS-VW tungsten-coated divertor in experiments with neon gas seeding

Nuclear Materials and Energy, 2023
Collector probes have been used to examine tungsten divertor leakage in a variety of scenarios with low-Z impurity seeding during operation with the new tungsten-coated SAS-VW divertor in DIII-D.
Matthew S. Parsons, Jeremy D. Mateja, Seth H. Messer, Tyler Abrams, Jean Paul Allain, Alessandro Bortolon, Patrick Byrne, David C. Donovan, Florian Effenberg, Jeffrey L. Herfindal, Florian Laggner, Tomas Odstrcil, Jun Ren, Dmitry L. Rudakov, Gregory Sinclair, Robert S. Wilcox   +15 more
doaj   +1 more source

Refining light impurity content estimates at the lower divertor based on experimental data in WEST

Nuclear Materials and Energy, 2023
WEST is an actively cooled, long-pulse tokamak with nearly all plasma-facing components (PFC) made of tungsten (W). One of the aims of WEST is to study plasma operation with W PFCs in preparation for long-pulse operation on W divertor devices like ITER ...
A. Grosjean, D.C. Donovan, C.A. Johnson, J.P. Gunn, C. Guillemaut, N. Fedorczak, C.C. Klepper, E.A. Unterberg   +7 more
doaj   +1 more source