Results 1 to 10 of about 8,268 (229)

Impurity radiation seeding of neoclassical tearing mode growth

open access: yesNuclear Fusion
The physics of neoclassical tearing modes (NTMs) is of great concern to tokamak plasma stability and performance, especially in the burning plasma regime.
Shiyong Zeng, Ping Zhu, Eric C. Howell
doaj   +3 more sources

Impurity-seeded plasma experiments on JET [PDF]

open access: yesNuclear Fusion, 2002
Scaling to larger tokamaks of high confinement plasmas with radiating edges, induced by impurities, is being studied through internationally collaborative experiments on JET. In campaigns till the end of 2000, three different regimes have been explored. A small number of limiter L-mode discharges seeded with neon have most closely repeated the approach
G.P Maddison   +43 more
openaire   +4 more sources

Long-pulse H-mode operation with stored-energy monitoring for detachment feedback control with a new lower tungsten divertor in EAST

open access: yesNuclear Fusion, 2023
One of the key challenges for future fusion research is to mitigate the high steady-state heat load on the divertor target plates, and divertor detachment offers a promising solution. The Experimental Advanced Superconducting Tokamak (EAST) has developed
Y.Q. Tao   +24 more
doaj   +1 more source

Overview of ASDEX Upgrade results [PDF]

open access: yes, 2017
The ASDEX Upgrade (AUG) programme is directed towards physics input to critical elements of the ITER design and the preparation of ITER operation, as well as addressing physics issues for a future DEMO design.
ASDEX Upgrade Team   +2 more
core   +4 more sources

Divertor Impurity Seeding Experiments at the COMPASS Tokamak [PDF]

open access: yesNuclear Fusion, 2019
Partial detachment is the desired regime for the baseline burning plasma scenario in ITER and other next-step devices, as it allows for the dissipation of the majority of the energy carried by charged particles through the scrape-off-layer and thus avoids localised heat flux deposition in the divertor region.
Komm, M.   +25 more
openaire   +5 more sources

Mechanism of enhanced ion temperature by impurity seeding in EAST H-mode plasma

open access: yesNuclear Fusion, 2023
Ion temperature ( T _i ) profiles are commonly observed to increase in peaking, leading to higher central T _i , after impurity seeding in the EAST H-mode plasma. Argon can be more efficient at raising T _i than neon.
Xiuda Yang   +22 more
doaj   +1 more source

Predictive modelling of impurity seeded plasmas in JET [PDF]

open access: yesPlasma Physics and Controlled Fusion, 2002
Seeding of impurities into JET resulted in a pronounced modification of plasma confinement properties. In order to analyse the underlying mechanisms a predictive transport modelling has been performed by means of two approaches. (i) The Chalmers advanced fluid model for temperature gradient driven instabilities is applied to determine all transport ...
M Z Tokar   +6 more
openaire   +3 more sources

Improved ELM scaling with impurity seeding in JET [PDF]

open access: yesPlasma Physics and Controlled Fusion, 2003
Argon-seeded H-modes in low triangularity pumped-limiter-like, and medium to high triangularity divertor, configurations on JET are described, focusing upon ELM effects. Appropriate fuelling and seeding strategies in each geometry have combined good confinement with density around the Greenwald level, accompanied by ELMS shown to have explicitly Type I
Maddison, G. P.   +10 more
  +6 more sources

Direct Gyrokinetic Comparison of Pedestal Transport in JET with Carbon and ITER-Like Walls [PDF]

open access: yes, 2019
This paper compares the gyrokinetic instabilities and transport in two representative JET pedestals, one (pulse 78697) from the JET configuration with a carbon wall (C) and another (pulse 92432) from after the installation of JET's ITER-like Wall (ILW ...
Field, A. R.   +11 more
core   +2 more sources

Impurity control study of radiative tungsten divertor in EAST tokamak

open access: yesNuclear Materials and Energy, 2020
EAST was equipped with W-coated divertor plates and dome for the upper divertor, the remaining plasma facing components include the plasma facing components at lower divertor consisted of Carbon materials, at the baffles and main chamber walls consisted ...
YiPing Chen   +4 more
doaj   +1 more source

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