Results 31 to 40 of about 246 (87)

Modelling study of divertor W leakage for different divertor conditions with Ne seeding in EAST tokamak

Nuclear Fusion
Sequential SOLPS-ITER and DIVIMP simulations are carried out for tungsten (W) edge transport during neon (Ne) injection in EAST, elucidating the pathway of W impurity leakage from the divertor to the core plasma under different dissipative divertor ...
Guoliang Xu, Hui Wang, Rui Ding, Hang Si, Guozhang Jia, Jin Guo, Hai Xie, Rong Yan, Ran Hai, Dahuan Zhu, Junling Chen   +10 more
doaj   +1 more source

Simulation study of the influence of the outer target geometry on tungsten contamination: Horizontal vs. vertical target

Nuclear Materials and Energy
The core tungsten (W) concentration must be limited to an extremely low level for future fusion reactors. It was found that the effects of E × B drift can lead to a dramatic increase in the core W concentration in our recent work [J.
Hongxin Ding, Jin Guo, Shifeng Mao, Xinglei Ruan, Yuchen Xu, Minyou Ye   +5 more
doaj   +1 more source

WEST Physics Basis [PDF]

, 2015
With WEST (Tungsten Environment in Steady State Tokamak) (Bucalossi et al 2014 Fusion Eng. Des. 89 907-12), the Tore Supra facility and team expertise (Dumont et al 2014 Plasma Phys. Control.
Artaud, J. F., Basiuk, V., Becoulet, M., Bourdelle, C., Bremond, S., Bucalossi, J., García Muñoz, Manuel, Jet Contributors   +7 more
core   +1 more source

Radiative divertor studies in JET high confinement mode plasmas [PDF]

, 2015
Controlled power exhaust is one of the key challenges in reactor scale fusion devices. These devices must maintain heat loads less than 10 MW/m2 at the plasma-facing materials (PFM), while producing gigawatts of fusion power.
Järvinen, Aaro
core   +1 more source

Drifts effect on the divertor W leakage mechanisms under different dissipative divertor conditions of EAST

Nuclear Fusion
A new drift module has been developed in the DIVIMP code, enabling two-dimensional simulations of tungsten (W) transport in the edge plasma with full drifts included.
Hui Wang, Guoliang Xu, Rui Ding, Hang Si, Guozhang Jia, Hai Xie, Ran Hai, Zhibin Wang, Dahuan Zhu, Rong Yan, Junling Chen   +10 more
doaj   +1 more source

Code/Code comparison of impurity transport in EMC3 and DIVIMP [PDF]

Physica Scripta, 2020
Schmid, K, Lunt, T, Zhang, W
openaire   +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   +1 more source

ERO modelling of net and gross erosion of marker samples exposed to L-mode plasmas on ASDEX Upgrade [PDF]

, 2020
In this paper, we report experimental and numerical investigations of gross and net erosion of gold (Au) and molybdenum (Mo), proxies for the common plasma-facing material tungsten (W), during L-mode plasma discharges in deuterium (D) in the outer strike-
Airila, M., ASDEX Upgrade Team, Balden, M., Cavedon, M., EUROfusion MST1 Team, Groth, M., Hakola, A., Keitaanranta, A., Krieger, K., Kumpulainen, H., Lahtinen, A., Likonen, J.   +11 more
core   +2 more sources

Design Strategy for the PFC in DEMO Reactor (KIT Scientific Reports ; 7637) [PDF]

, 2013
The performance of the plasma facing components (PFC) and materials in fusion reactor DEMO are fundamental issues affecting the ultimate technological and economic feasibility of fusion power.
Bazylev, B., Fetzer, R., Igitkhanov, Yuri, Landman, I.   +3 more
core   +2 more sources

The Application of Mass Spectrometry Techniques for the Benefit of Tungsten Impurity Transport Research and Nuclear Fusion [PDF]

, 2017
Several barriers prevent the capability of on the grid nuclear fusion power plants. With the research presented here, these issues are confronted and the work makes progress towards addressing known gaps in the fusion community’s understanding of ...
Duran, Jonah David
core   +1 more source