Results 51 to 60 of about 973 (141)

Comparing N versus Ne as divertor radiators in ASDEX-upgrade and ITER

open access: yesNuclear Materials and Energy, 2019
The study aims to estimate the influence of machine scale size on the behavior of plasma with extrinsic seeded impurities in the scrape-off layer (SOL) and divertor.
Elizaveta Sytova   +9 more
doaj   +1 more source

High-order Discretization of a Gyrokinetic Vlasov Model in Edge Plasma Geometry

open access: yes, 2017
We present a high-order spatial discretization of a continuum gyrokinetic Vlasov model in axisymmetric tokamak edge plasma geometries. Such models describe the phase space advection of plasma species distribution functions in the absence of collisions ...
Colella, Phillip   +5 more
core   +1 more source

Spectroscopic investigations of detachment on the MAST Upgrade Super-X divertor [PDF]

open access: yes, 2022
We present the first analysis of the atomic and molecular processes at play during detachment in the MAST-U Super-X divertor using divertor spectroscopy data.
A. Fil   +21 more
core   +3 more sources

SOLPS-ITER simulations of a vapour box design for the linear device Magnum-PSI [PDF]

open access: yes, 2023
A vapour box (VB) is a physical device currently being considered to reduce the high heat and particle fluxes typically impacting the divertor in tokamaks.
Gonzalez, J.   +2 more
core   +1 more source

Modeling of tungsten impurity transport and distribution in EAST based on multi-fluid and kinetic Monte Carlo simulations

open access: yesAIP Advances
In recent years, the materials of plasma facing components, such as divertor target plates, domes, and outer walls of tokamaks, such as ASDEX Upgrade, WEST, JET, EAST, and ITER, have been changed from carbon to tungsten because of its lower erosion and ...
Ziyang Wen, YiPing Chen, Ling Zhang
doaj   +1 more source

Predictive SOLPS-ITER simulations to study the role of divertor magnetic geometry in detachment control in the MAST-U Super-X configuration

open access: yesNuclear Fusion, 2023
The SOLPS-ITER code has been utilised to study the movement of the detachment front location from target towards the X-point for MAST-U Super-X plasmas.
O. Myatra   +7 more
doaj   +1 more source

Novel SOLPS-ITER simulations of X-point target and snowflake divertors

open access: yesPlasma Physics and Controlled Fusion, 2023
Abstract The design and understanding of alternative divertor configurations may be crucial for achieving acceptable steady-state heat and particle material loads for magnetic confinement fusion reactors. Multiple X-point alternative divertor geometries such as snowflakes and X-point targets have great potential in reducing power loads ...
C Cowley   +9 more
openaire   +2 more sources

Coupling Fluid Neutrals to Gyrokinetic Plasma Dynamics for Edge and SOL Turbulence Simulations

open access: yesContributions to Plasma Physics, EarlyView.
ABSTRACT Accurate modeling of turbulent transport in magnetic confinement fusion devices requires extending first‐principles gyrokinetic simulations from the core to the edge and scrape‐off layer (SOL), where additional physics—particularly plasma–neutrals interactions—must be included.
Sabine Ogier‐Collin   +3 more
wiley   +1 more source

2D Implementation of Kinetic‐Diffusion Monte Carlo in Eiron

open access: yesContributions to Plasma Physics, EarlyView.
ABSTRACT Particle‐based kinetic Monte Carlo simulations of neutral particles are one of the major computational bottlenecks in tokamak scrape‐off layer simulations. This computational cost comes from the need to resolve individual collision events in high‐collisional regimes.
Oskar Lappi   +3 more
wiley   +1 more source

First SOLPS‐ITER simulations of ASDEX Upgrade partially detached H‐mode with boron impurity: The missing radiation at the outer strike‐point region

open access: yesContributions to Plasma Physics, Volume 64, Issue 7-8, August-September 2024.
Abstract Partially detached H‐modes are the baseline regime for the future ITER operation. The ASDEX Upgrade partially detached H‐mode is modeled using the SOLPS‐ITER code with drifts enabled and compared with experimental data. For the first time, boron (B) impurity is simulated in the Scrape‐off layer (SOL) and divertor. A comparison between divertor
S. O. Makarov   +10 more
wiley   +1 more source

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