Results 21 to 30 of about 217 (90)

Performance Analysis and Optimizations of ERO2.0 Fusion Code [PDF]

open access: yesProceedings of the Platform for Advanced Scientific Computing Conference
Peer ...
Garcia-Gasulla, Marta   +4 more
openaire   +3 more sources

A sensitivity analysis of numerical predictions for beryllium erosion and migration in ITER

open access: yesNuclear Materials and Energy, 2021
The present study addresses the uncertainties that affect the recently performed predictions of beryllium (Be) erosion and migration in ITER using the Monte-Carlo code ERO2.0. The focus of the study is a D–T baseline discharge with fusion power gain Q=10,
J. Romazanov   +10 more
doaj   +3 more sources

Global tungsten erosion and migration modeling for the EU-DEMO with the ERO2.0 code

open access: yesNuclear Fusion
Global tungsten migration, thus erosion, transport, and deposition, in the EU-DEMO tokamak is investigated using ERO2.0 simulations for an argon-seeded ELM-free H-mode plasma scenario with expected 2 GW fusion power developed with the narrow-grid version
C. Baumann   +7 more
doaj   +3 more sources

Angular distribution dependence of W migration on the ITER divertor from ERO2.0 simulations

open access: yesNuclear Fusion
The tungsten (W) surface of the ITER divertor might provide suitable surface temperatures and helium (He) influxes for the formation of microscopic fuzz structures.
F. Chang   +6 more
doaj   +3 more sources

Exploring the role of topography in the sputtering process of tungsten by GyM helium plasma [PDF]

open access: yesNuclear Fusion
This work investigates the role of surface topography in the sputtering process of tungsten (W) exposed to helium plasma using the GyM linear device.
Andrea Uccello   +15 more
doaj   +2 more sources

An update of Tritium co-deposition in ITER using WallDYN3D

open access: yesNuclear Materials and Energy, 2022
The retention by co-deposition of fuel species in Be-layers, forming due to migration of Be eroded from the 3D-shaped main chamber wall in ITER, was modeled with WallDYN-3D.
K. Schmid
doaj   +1 more source

Model validation of tungsten erosion and redeposition properties using biased tungsten samples on DiMES

open access: yesNuclear Materials and Energy, 2023
An experiment was performed in the DIII-D lower divertor to validate numerical SOL tungsten (W) impurity erosion and redeposition simulations against experimental data. The net and gross erosion of W were calculated as a function of the voltage (or bias)
L. Cappelli   +14 more
doaj   +1 more source

First 3D modelling of tungsten erosion and migration in WEST discharges adopting a toroidally non-symmetric wall geometry

open access: yesNuclear Materials and Energy, 2023
Numerical analysis is a useful tool to investigate tungsten (W) sources and transport across plasma in W Environment Steady state Tokamak (WEST) plasma discharges, as it highlights physical mechanisms not always directly observable in experiments ...
S. Di Genova   +10 more
doaj   +1 more source

Laser ablation molecular isotopic spectroscopy: A novel tool to characterise the distribution of 13C and 12C on graphite after 13CH4 tracer injection in Wendelstein 7-X

open access: yesNuclear Materials and Energy, 2022
Wendelstein 7-X (W7-X) operation with inertially cooled graphite Test Divertor Unit (TDU) was finalised in a series of identical hydrogen plasmas with injection of 13C isotopically marked methane. The break-up of 13CH4, injected through gas inlets at one
E. Wüst   +4 more
doaj   +1 more source

Implementation of the Homogeneous Mixing Model in the ERO2.0 Code

open access: yes, 2021
Implementation of the Homogeneous Mixing Model in the ERO2.0 CodeM. Navarro1, J. Romazanov2, A. Eksaeva2, D. Matveev2, D. Borodin2, A. Kirschner2, E.T. Hinson1, O.
Kirschner, A.   +6 more
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