Results 31 to 40 of about 14,440 (202)

A survey of problems in divertor and edge plasma theory [PDF]

, 1992
Theoretical physics problems related to divertor design are presented, organized by the region in which they occur. Some of the open questions in edge physics are presented from a theoretician`s point of view.
Houlberg, W., Wootton, A., Braams, B., Weitzner, H., Hinton, F., Post, D., Sadowski, W., Sigmar, D., Cohen, R., Hazeltine, R., Boozer, A., Oktay, E.   +11 more
core   +3 more sources

Analysis of indefinite divertor footprint with proper orthogonal decomposition in hydrogen/deuterium plasmas in LHD

Nuclear Materials and Energy, 2019
Divertor particle flux signals on divertor plates were analyzed with the multivariable analysis technique, namely, proper orthogonal decomposition (POD), to characterize the indefinite divertor footprint in the Large Helical Device.
H. Tanaka, S. Masuzaki, G. Kawamura, M. Kobayashi, Y. Suzuki, T. Morisaki, N. Ohno   +6 more
doaj   +1 more source

Experimental evidence for the drift wave nature of the weakly coherent mode in ASDEX Upgrade I-mode plasmas

Nuclear Fusion
The improved energy confinement mode (I-mode) is a potential candidate for future fusion power plants, as it combines ELM-free operation with good confinement. The unusual edge transport and turbulence in this regime is still not fully understood.
M. Herschel, T. Happel, D. Wendler, M. Griener, J. Kalis, R. Fischer, P. Manz, U. Stroth, the ASDEX Upgrade Team   +8 more
doaj   +1 more source

Interpretations of the impact of cross-field drifts on divertor flows in DIII-D with UEDGE

Nuclear Materials and Energy, 2017
Simulations using the multi-fluid code UEDGE indicates that, in low confinement (L-mode) plasmas in DIII-D, poloidal projection of the ionization driven flows dominate poloidal particle flows in the divertor near the divertor plates, whereas E ×B drift ...
A.E. Jaervinen, S.L. Allen, M. Groth, A.G. McLean, T.D. Rognlien, C.M. Samuell, A. Briesemeister, M. Fenstermacher, D.N. Hill, A.W. Leonard, G.D. Porter   +10 more
doaj   +1 more source

ELM heat flux in the ITER divertor [PDF]

, 1998
Edge-Localized-Modes (ELMs) have the potential to produce unacceptable levels of erosion of the ITER divertor. Ablation of the carbon divertor target will occur if the surface temperature rises above about 2,500 C.
Herrmann, A., Osborne, T.H., Hermann, A., Osborne, T., Lingertat, J., Leonard, A., Suttrop, W., Itami, K., Leonard, A.W., Loarte, A.   +9 more
core  

Effect of divertor legs on neutral particle and impurity retention for a closed helical divertor configuration in the Large Helical Device

, 2011
A closed helical divertor (CHD) has been designed for efficient particle control in the plasma periphery and for retaining neutral particles and impurity ions in the divertor region.
LHD, Experiment Group, MORISAKI, Tomohiko, SHOJI, Mamoru, MASUZAKI, Suguru, SAKAMOTO, Ryuichi, YAMADA, H.   +5 more
core   +1 more source

Temporal characteristics of ELMs on the COMPASS divertor

Nuclear Fusion, 2023
The presented work shows a systematic study of the temporal characteristics of ELM events on the COMPASS divertor obtained with high temporal resolution probe measurements (∼1 μ s).
J. Adamek, J. Cavalier, D. Tskhakaya, B. Csillag, L. Cinnirella, J. Lips, D. Lopez-Rodriguez, D. Sosa, D. Medina, P. Vondracek, L. Kripner, M. Komm, M. Sos, H. Lindl, the COMPASS Team   +14 more
doaj   +1 more source

Assessment of X-point target divertor configuration for power handling and detachment front control

Nuclear Materials and Energy, 2017
A study of long-legged tokamak divertor configurations is performed with the edge transport code UEDGE (Rognlien et al., J. Nucl. Mater. 196, 347, 1992). The model parameters are based on the ADX tokamak concept design (LaBombard et al., Nucl. Fusion 55,
M.V. Umansky, M.E. Rensink, T.D. Rognlien, B. LaBombard, D. Brunner, J.L. Terry, D.G. Whyte   +6 more
doaj   +1 more source

Measurements and modeling of type-I and type-II ELMs heat flux to the DIII-D divertor

Nuclear Fusion, 2023
Type-I and type-II edge-localized-modes (ELMs) heat flux profiles measured at the DIII-D divertor feature a peak in the vicinity of the strike-point and a plateau in the scrape-off-layer (SOL), which extends to the first wall.
R. Perillo, J.A. Boedo, C.J. Lasnier, R.A. Pitts, M. Brank, I. Bykov, J.D. Coburn, F. Glass, C. Marini, T. Osborne, M. Riding, D.L. Rudakov, J.G. Watkins, L. Zeng   +13 more
doaj   +1 more source

Simulation Analysis of the Design of a Vacuum Pumping System for the Closed Helical Divertor in the Large Helical Device

, 2011
A promising candidate of a vacuum pumping system for the closed helical divertor in the large helical device is proposed using a three-dimensional neutral particle transport simulation code (EIRENE) and a finite element based multi-physics analysis ...
MORISAKI, Tomohiro, YAMADA, Hiroshi, KOBAYASHI, Masahiro, SHOJI, Mamoru, TOKITANI, Masayuki, MASUZAKI, Suguru, SAKAMOTO, Ryuichi, TAKEIRI, Yasuhiko   +7 more
core   +1 more source