Results 61 to 70 of about 144 (106)

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

Modeling of impurity seeding and transport for W7-X island divertor scenarios with EMC3-EIRENE

, 2017
http://fusionsites.ciemat.es/cwgm16/files/2017/01/effenberg_16thCWGM_Madrid2017 ...
Effenberg, Florian, Feng, Y., Schmitz, O., Frerichs, H., Blackwell, B., Barbui, T., Geiger, J., Bozhenkov, S., Jakubowski, M., König, R., Krychowiak, M., Niemann, H., Sunn Pedersen, T., Stephey, L., Suzuki, Y., Wurden, G.A.   +15 more
openaire   +2 more sources

Full-torus impurity transport simulation in boron powder injection experiments in the Large Helical Device

Nuclear Materials and Energy
The toroidal distribution of boron deposition on plasma-facing components (PFCs) in boron powder injection using an impurity power dropper (IPD) was investigated by full-torus simulation and observations in a systematic plasma density-scan experiment ...
M. Shoji, G. Kawamura, R. Smirnov, J. Romazanov, A. Kirschner, Y. Tanaka, S. Masuzaki, T. Kawate, F. Nespoli, R. Lunsford, E.P. Gilson, S. Brezinsek, N.A. Pablant   +12 more
doaj   +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

Comparison of plasma response models for RMP effects on the divertor and scrape-off layer in KSTAR

Nuclear Fusion
Resonant magnetic perturbations (RMPs) are beneficial for control of edge localized modes (ELMs) in tokamaks. Nevertheless, a side effect of RMPs is the appearance of helical striations in the particle and heat loads onto divertor targets. The extent and
H. Frerichs, J. Van Blarcum, T. Cote, S.K. Kim, Y.Q. Liu, S.M. Yang   +5 more
doaj   +1 more source

Integrated modeling of boron powder injection for real-time plasma-facing component conditioning

Nuclear Materials and Energy
An integrated modeling framework for investigating the application of solid boron (B) powder injection for real-time surface conditioning of plasma-facing components (PFCs) in tokamak environments is presented.
F. Effenberg, K. Schmid, F. Nespoli, A. Bortolon, Y. Feng, B.A. Grierson, J.D. Lore, R. Maingi, D.L. Rudakov   +8 more
doaj   +1 more source

Integrated simulation of the impacts of resonant magnetic perturbations on tungsten radiation on EAST

Nuclear Fusion
A significant reduction of 70% in tungsten (W) radiation intensity has been experimentally observed under resonant magnetic perturbation (RMP) fields on the EAST tokamak.
Z.H. Gao, S.Y. Dai, P. Qin, Z.X. Wen, Z.C. Lin, Z. Zhou, H.M. Zhang, G.Z. Hao, Y. Feng, D.Z. Wang   +9 more
doaj   +1 more source

EMC3-EIRENE simulations of edge plasma and impurity transport by toroidally localized argon seeding on CFETR X-divertor

Nuclear Fusion
The three-dimensional (3D) edge Monte Carlo transport code EMC3-EIRENE has been employed to study edge plasma and impurity transport with toroidally localized argon seeding using the Chinese fusion engineering testing reactor (CFETR) X-divertor ...
T. Xie, H. Li, W. Zhang, R. Ding, L. Wang, Y. Luo, D.Z. Wang   +6 more
doaj   +1 more source

Off-target gradient-driven flows in 3D simulations of ADITYA-Upgrade tokamak scrape-off layer plasma transport

Nuclear Fusion
Coupled plasma-neutral transport simulations are performed on ADITYA-Upgrade tokamak scrape-off layer (SOL) plasma, where flows in the core and SOL were measured to reverse signs with density variation.
Arzoo Malwal, Bibhu Prasad Sahoo, Devendra Sharma, Yühe Feng   +3 more
doaj   +1 more source

Taming harmful bursts and heat flux in high-confinement tokamak plasmas. [PDF]

Nat Commun
Hu QM, Wang HQ, Navarro M, Wang HH, Eldon D, Gu S, Ma XX, Frerichs H, Scotti F, Wang L, Wilcox RS, Wilks TM, Bortolon A, Ceelen L, Effenberg F, Gong XZ, Jia MN, Kim SK, Lasnier CJ, Leonard AW, Li KD, Logan NC, Ma Q, Maingi R, Meng LY, Moser AL, Osborne TH, Paz-Soldan C, Shafer MW, Sun YW, Yang SM, Ye C.   +31 more
europepmc   +1 more source