Results 91 to 100 of about 14,440 (202)

Parallel flows as a key component to interpret Super-X divertor experiments

open access: yesNuclear Fusion
The Super-X Divertor (SXD) is an alternative divertor configuration leveraging total flux expansion at the Outer Strike Point (OSP). While the extended 2-Point Model (2PM) predicts facilitated detachment access and control in the SXD configuration, these
M. Carpita   +17 more
doaj   +1 more source

High performance power handling in the absence of an H-mode edge in negative triangularity DIII-D plasmas

open access: yesNuclear Fusion
Experiments performed during strongly-shaped high-power diverted negative triangularity (NT) experiments in DIII-D achieved detached divertor conditions and a transient-free edge, showcasing the potential for application of NT to a core-edge integrated ...
F. Scotti   +21 more
doaj   +1 more source

Simulation study on global migration of locally generated impurity in JT-60U

open access: yesNuclear Materials and Energy
The transport of carbon and neon particles locally emitted from plasma facing components under the JT-60U L-mode plasma condition is investigated by the integrated divertor code SONIC. In this analysis, an impurity point source emitting a small amount of
Ryuichi Sano   +2 more
doaj   +1 more source

The effect of divertor closure on the impurity stagnation point in detached L-mode discharges on DIII-D

open access: yesNuclear Materials and Energy
This paper presents experimental measurements of the location of the impurity flow stagnation point in the scrape-off-layer (SOL) of a tokamak plasma. Coherence imaging of carbon-2+ emission (465 nm) is used to track the main-chamber impurity velocity of
M.G. Burke   +9 more
doaj   +1 more source

Optimization of lithium vapor box divertor evaporator location on NSTX-U using SOLPS-ITER

open access: yesNuclear Fusion
Commercial fusion reactors will be faced with extremely high divertor target heat fluxes that will require mitigation. Simulations of detachment in an NSTX-U scenario projected to have 92 MW m ^−2 unmitigated peak target heat flux are presented, which ...
E.D. Emdee   +3 more
doaj   +1 more source

WEST full tungsten operation with an ITER grade divertor

open access: yesNuclear Fusion
The mission of WEST (tungsten-W Environment in Steady-state Tokamak) is to explore long pulse operation in a full tungsten (W) environment for preparing next-step fusion devices (ITER and DEMO) with a focus on testing the ITER actively cooled W divertor ...
J. Bucalossi   +390 more
doaj   +1 more source

Enhanced thermal fatigue resistance of W/Cu divertor components via serrated interface design: experimental and numerical insights

open access: yesNuclear Fusion
Divertors constructed primarily from tungsten–copper (W/Cu) composites are essential components in magnetically confined fusion reactors, where they are subjected to extreme thermal loads.
Menglai Jiang   +8 more
doaj   +1 more source

Study of passively stable, fully detached divertor plasma regimes attained in innovative long-legged divertor configurations

open access: yes
Numerical modeling of divertor configurations with radially or vertically extended, tightly baffled, outer divertor legs has demonstrated the existence of a passively-stable fully detached divertor regime.
Umansky, M.V.; Labombard, B.; Brunner, D.; Golfinopoulos, T.; Kuang, A.Q.; Rensink, M.E.; Terry, J.L.; Wigram, M.; Whyte, D.G.
core   +1 more source

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