Results 21 to 30 of about 39,641 (298)

Density dependence of SOL power width in ASDEX upgrade L-Mode

Nuclear Materials and Energy, 2017
Understanding the heat transport in the scrape-off layer (SOL) and the divertor region is essential for the design of large fusion devices such as ITER and DEMO.
B. Sieglin, T. Eich, M. Faitsch, A. Herrmann, D. Nille, A. Scarabosio, ASDEX Upgrade Team   +6 more
doaj   +1 more source

Fluctuation characteristics of the TCV snowflake divertor measured with high speed visible imaging [PDF]

, 2018
Tangentially viewing fast camera footage of the low-field side snowflake minus divertor in TCV is analysed across a four point scan in which the proximity of the two X-points is varied systematically.
Farley, T., Harrison, J., Innocente, P., Labit, B., Militello, F., Reimerdes, H., Team, the MST1, Team, the TCV, Walkden, N. R.   +8 more
core   +2 more sources

Evaluation of ITER divertor shunts as a synthetic diagnostic for detachment control

Nuclear Fusion, 2023
Reliable diagnostics that measure the detached state of the ITER divertor plasma will be necessary to control heat flux to the divertor targets during steady state, burning plasma operation. This paper conducts an initial exploration into the feasibility
C.A. Orrico, T. Ravensbergen, R.A. Pitts, X. Bonnin, E. Kaveeva, J.S. Park, V. Rozhansky, I. Senichenkov, C. Watts, M. de Baar   +9 more
doaj   +1 more source

Experimental Divertor Similarity Database Parameters [PDF]

, 1995
A set of experimentally-determined dimensionless parameters is proposed for characterizing the regime of divertor operation. The objective is to be able to compare as unambiguously as possible the operation of different divertors and to understand what ...
Hutchinson, I. H., LaBombard, B., Lipschultz, B.   +2 more
core   +4 more sources

The I-mode confinement regime at ASDEX Upgrade: global propert ies and characterization of strongly intermittent density fluctuations [PDF]

, 2016
Properties of the I­mode confinement regime on the ASDEX Upgrade tokamak are summarized. A weak dependence of the power threshold for the L­I transition on the toroidal magnetic field strength is found.
Bernert, M., Conway, G., Dunne, M., Guimarais, L., Happel, T., Hennequin, P., Hetzenecker, A., Honore, C., Manz, P., Maraschek, M., Ryter, F., Stroth, U., Viezzer, E.   +12 more
core   +5 more sources

Investigation of the particle accumulation effects on the power exhaust of snowflake minus divertor on HL-2M tokamak by SOLPS-ITER

Nuclear Materials and Energy, 2020
To solve the power exhaust handling challenge, meanwhile maintaining acceptable divertor target erosion, the snowflake divertor (SFD) is proposed on HL-2M tokamak. In this work, simulations are carried out by using scrape-off layer plasma simulation code
Yanjie Zhang, Chaofeng Sang, Jiaxian Li, Guoyao Zheng, Chen Zhang, Daoyuan Liu, Dezhen Wang   +6 more
doaj   +1 more source

Benchmarking of a 1D Scrape-off layer code SOLF1D with SOLPS and its use in modelling long-legged divertors

, 2013
A 1D code modelling SOL transport parallel to the magnetic field (SOLF1D) is benchmarked with 2D simulations of MAST-U SOL performed via the SOLPS code for two different collisionalities. Based on this comparison, SOLF1D is then used to model the effects
Coster, D, Fishpool, G, Fundamenski, W, Havlickova, E, Subba, F, Wischmeier, M   +5 more
core   +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

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

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