Results 51 to 60 of about 973 (141)
Comparing N versus Ne as divertor radiators in ASDEX-upgrade and ITER
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
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]
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]
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
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
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
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
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
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
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

