Results 51 to 60 of about 261 (113)

Experimental and simulation study of helium plasma transport during ion cyclotron resonance heating in MPS-LD

open access: yesNuclear Fusion
The linear plasma devices (LPDs) can provide a good platform to experimentally simulate the divertor physics. MPS-LD is a new LPD, which uses ion cyclotron resonance heating (ICRH) to raise the ion temperature ( T _i ).
Changjiang Sun   +10 more
doaj   +1 more source

First SOLEDGE3X-EIRENE simulations of the ITER Neon seeded burning plasma boundary up to the first wall

open access: yesNuclear Materials and Energy
Boundary plasma simulations are essential to estimate expected divertor and first wall (FW) heat and particle loads on ITER during burning plasma operation.
S. Sureshkumar   +15 more
doaj   +1 more source

Transport in the tokamak - reactor edge plasma with strong collisionality

open access: yesNuclear Materials and Energy, 2022
In detached divertor regimes, especially in future tokamak-reactors, plasma in the divertor is strongly collisional. When ion-ion and ion-neutral collision frequencies become comparable with the ion gyrofrequency, plasma transport is strongly affected by
V. Rozhansky   +3 more
doaj   +1 more source

Autoregressive long-horizon prediction of plasma edge dynamics

open access: yesNuclear Fusion
Accurate modeling of scrape-off layer (SOL) and divertor-edge dynamics is vital for designing plasma-facing components in fusion devices. High-fidelity edge fluid/neutral codes such as SOLPS-ITER capture SOL physics with high accuracy, but their ...
Hunor Csala   +5 more
doaj   +1 more source

Mechanisms of XPR formation from SOLPS-ITER modeling

open access: yesPhysics of Plasmas
The early stages of X-point radiator (XPR) regime formation in a medium-size metal-wall tokamak with a single-null configuration and vertical divertor targets are discussed in detail, using the ASDEX Upgrade tokamak as an example. Based on the SOLPS-ITER modeling of ASDEX Upgrade with nitrogen (N) seeding, it is shown that the mechanisms associated ...
A. Poletaeva   +5 more
openaire   +1 more source

SOLPS-ITER modeling with activated drifts for a snowflake divertor in ASDEX Upgrade

open access: yesPlasma Physics and Controlled Fusion, 2020
Abstract We report on the first SOLPS-ITER simulations of a low-field side snowflake minus (LFS SF−) divertor configuration with drifts fully activated in ASDEX Upgrade. Compared to a reference case without drifts, the simulation in normal toroidal magnetic field configuration (B × ∇B points to the primary X-point) shows a larger low ...
O Pan   +4 more
openaire   +2 more sources

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

open access: yesNuclear 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   +9 more
doaj   +1 more source

On the role of atomic momentum and molecules in self-consistent 1D scrape-off layer simulation of MAST-U, using DIV1D

open access: yesNuclear Fusion
In this paper, the 1D physics-based dynamic scrape-off-layer (SOL) model DIV1D is extended to include molecular interactions and the effects of finite atomic flow velocity parallel to the magnetic field lines.
S.P. Kobussen   +5 more
doaj   +1 more source

Physics basis for the first ITER tungsten divertor

open access: yesNuclear Materials and Energy, 2019
On the eve of component procurement, this paper discusses the present physics basis for the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining the overall design, and outlining relevant aspects of the Research Plan ...
R.A. Pitts   +17 more
doaj   +1 more source

Deuterium retention in co-deposition with lithium in Magnum-PSI: experimental analysis and comparison with SOLPS-ITER

open access: yesNuclear Fusion
The vapor-box, a liquid metal design for the divertor, utilizes lithium recirculation through evaporation and condensation. Safety concerns arise from Li-D/T formation and co-deposition on vapor-box walls and the first wall, affecting tritium retention ...
M. Morbey   +4 more
doaj   +1 more source

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