A. Kirschner
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View article: Tungsten erosion and scrape-off layer transport modelling in L-mode helium plasma discharges in ASDEX Upgrade
Tungsten erosion and scrape-off layer transport modelling in L-mode helium plasma discharges in ASDEX Upgrade Open
Due to its unavoidable presence in thermonuclear DT plasmas and to its peculiar effects on materials, investigating the role of helium (He) in plasma-wall interaction (PWI) in current tokamaks is fundamental. In this work, PWI in L-mode He…
View article: SOLPS-ITER simulation of W limiter start-up on ITER
SOLPS-ITER simulation of W limiter start-up on ITER Open
The switch from beryllium (Be) to tungsten (W) first wall (FW) armor in the new ITER baseline Pitts et al (2025 Nucl. Mater. Energy 42 101854), Loarte (n.d. Plasma Phys. Control. Fusion ) will impact the limiter start-up phase due to the m…
View article: Improved erosion estimates for the STEP divertor
Improved erosion estimates for the STEP divertor Open
Net tungsten erosion and deposition profiles are simulated for the outer and inner lower divertor of STEP, a spherical prototype fusion reactor targeting ∼ 2040. In this contribution, previous modelling work [1] has been extended by studyi…
View article: Erosion and impurity transport for the edge localized mode suppression window in KSTAR
Erosion and impurity transport for the edge localized mode suppression window in KSTAR Open
A 3D analysis of plasma wall interactions and global impurity transport for the edge localized mode suppression window in KSTAR during H-Mode discharges has shown that carbon erosion at the divertor plates is a strong function of the reson…
View article: Modeling of plasma facing component erosion, impurity migration, dust transport and melting processes at JET-ILW
Modeling of plasma facing component erosion, impurity migration, dust transport and melting processes at JET-ILW Open
An overview of the modeling approaches, validation methods and recent main results of analysis and modeling activities related to the plasma-surface interaction (PSI) in JET-ILW experiments, including the recent H/D/T campaigns, is present…
View article: Multi-staged ERO2.0 simulation of material erosion and deposition in recessed mirror assemblies in JET and ITER
Multi-staged ERO2.0 simulation of material erosion and deposition in recessed mirror assemblies in JET and ITER Open
The deposition/erosion on optical diagnostic components—mirrors—is a critical issue in reactor class devices with long-pulsed high fluence plasma operation. The paper presents results of the three-dimensional Monte–Carlo code ERO2.0 for tw…
View article: Validation of the ERO2.0 code using W7-X and JET experiments and predictions for ITER operation
Validation of the ERO2.0 code using W7-X and JET experiments and predictions for ITER operation Open
The paper provides an overview of recent modelling of global material erosion and deposition in the fusion devices Wendelstein 7-X (W7-X), JET and ITER using the Monte-Carlo code ERO2.0. For validating the modelling tool in a three-dimensi…
View article: Small resonant magnetic perturbations result in three-dimensional material transport in the fusion plasma edge
Small resonant magnetic perturbations result in three-dimensional material transport in the fusion plasma edge Open
Erosion patterns in a 3D magnetic topology are significantly altered when compared to an axisymmetric scenario due to differences in the impurity transport in a plasma environment. When resonant magnetic perturbations are applied in L-Mode…
View article: Multi-staged ERO2.0 simulation of material erosion and deposition in recessed ITER mirror assemblies
Multi-staged ERO2.0 simulation of material erosion and deposition in recessed ITER mirror assemblies Open
In reactor class devices, with long pulse, high fluence plasma operation and with diagnostic systems that cannot easily be maintained, a critical issue is the deposition/erosion of wall materials and its impact on key optical diagnostic co…
View article: Erosion estimates for the divertor and main wall components from STEP
Erosion estimates for the divertor and main wall components from STEP Open
The tungsten erosion within Spherical Tokamak for Energy Production (STEP) assuming tungsten main wall and tungsten divertor has been estimated with ERO at the inner and outer divertor, at the inner and outer midplane and at the outboard b…
View article: Multiphysics Modeling of Impurity Transport for FNSF Startup Scenario with ERO2.0
Multiphysics Modeling of Impurity Transport for FNSF Startup Scenario with ERO2.0 Open
This paper focuses on performing a multiphysics study using the ERO2.0 and UEDGE codes for two standard double null configurations for the Fusion Nuclear Science Facility: (a) 100% recycling and (b) 99% recycling. Results show that the mai…
View article: Validation of the plasma-wall interaction simulation code ERO2.0 by the analysis of tungsten migration in the open divertor region in the Large Helical Device
Validation of the plasma-wall interaction simulation code ERO2.0 by the analysis of tungsten migration in the open divertor region in the Large Helical Device Open
Tungsten migration in the open divertor region in the Large Helical Device is analyzed for validating the three-dimensional plasma-wall interaction simulation code ERO2.0. The ERO2.0 simulation reproduced the measurement of localized tungs…
View article: Control of tungsten impurity source and edge transport using different gas injection with full tungsten divertor on EAST
Control of tungsten impurity source and edge transport using different gas injection with full tungsten divertor on EAST Open
Tungsten (W) erosion and edge transport are investigated for EAST L-mode discharges with different gas injection. It is found that W erosion can be suppressed or mitigated by Ne or D2 seeding when divertor detachment is achieved. Compared …
View article: Simulation Analysis of the Carbon Deposition Profile on Directional Material Probes in the Large Helical Device Using the ERO2.0 Code
Simulation Analysis of the Carbon Deposition Profile on Directional Material Probes in the Large Helical Device Using the ERO2.0 Code Open
The carbon deposition profile on a Directional Material Probe (DMP) installed in the inboard side of the torus in the Large Helical Device (LHD) is investigated using the ERO2.0 code. The experimental result of the carbon deposition profil…
View article: Beryllium erosion and redeposition in ITER H, He and D–T discharges
Beryllium erosion and redeposition in ITER H, He and D–T discharges Open
The Monte-Carlo code ERO2.0 was used to simulate steady-state erosion and transport of beryllium (Be) in the ITER main chamber. Various plasma scenarios were tested, including a variation of the main species (hydrogen, deuterium, helium), …
View article: Plasma-wall interaction studies in W7-X: main results from the recent divertor operations
Plasma-wall interaction studies in W7-X: main results from the recent divertor operations Open
Wendelstein 7-X (W7-X) is an optimized stellarator with a 3-dimensional five-fold modular geometry. The plasma-wall-interaction (PWI) investigations in the complex 3D geometry of W7-X were carried out by in situ spectroscopic observations,…
View article: Understanding tungsten erosion during inter/intra-ELM periods in He-dominated JET-ILW plasmas
Understanding tungsten erosion during inter/intra-ELM periods in He-dominated JET-ILW plasmas Open
Tungsten erosion was quantified during inter/intra-ELM periods in He-dominated JET-ILW plasmas by optical emission spectroscopy. The intra-ELM tungsten sputtering in helium plasmas, which dominates the total W source, prevails by a factor …
View article: Latest results of Eurofusion plasma-facing components research in the areas of power loading, material erosion and fuel retention
Latest results of Eurofusion plasma-facing components research in the areas of power loading, material erosion and fuel retention Open
The interaction between the edge-plasma in a fusion reactor and the surrounding first-wall components is one of the main issues for the realisation of fusion energy power plants. The EUROfusion Work Package on plasma-facing components addr…
View article: Interpretative modeling of impurity transport and tungsten sources in WEST boundary plasma
Interpretative modeling of impurity transport and tungsten sources in WEST boundary plasma Open
International audience
View article: Simulation of Impurity Transport and Deposition in the Closed Helical Divertor in the Large Helical Device
Simulation of Impurity Transport and Deposition in the Closed Helical Divertor in the Large Helical Device Open
Long pulse discharges in the Large Helical Device have often been interrupted by large amounts of dust particle emission from the divertor region caused by the exfoliation of carbon-rich mixed material deposition layers. The plasma wall in…
View article: A sensitivity analysis of numerical predictions for beryllium erosion and migration in ITER
A sensitivity analysis of numerical predictions for beryllium erosion and migration in ITER Open
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 …
View article: Erosion and screening of tungsten during inter/intra-ELM periods in the JET-ILW divertor
Erosion and screening of tungsten during inter/intra-ELM periods in the JET-ILW divertor Open
Intra-ELM tungsten sources, which dominate the total W source, are quantified in the inner and outer divertor of JET-ILW. The amount of the sputtered W atoms for individual ELMs demonstrates a clear dependence on the ELM frequency. It decr…
View article: 13C tracer deposition in EAST D and He plasmas investigated by high-throughput deuteron nuclear reaction analysis mapping
13C tracer deposition in EAST D and He plasmas investigated by high-throughput deuteron nuclear reaction analysis mapping Open
Rare isotope tracer injection represents an established way for following particle transport in fusion research, but a tracer experiment is only as good as the tracer can be followed and separated from the common isotope. Physical models f…
View article: First application of the massively-parallel Monte Carlo code ERO2.0 for plasma-wall interaction and 3D local impurity transport at JET ILW
First application of the massively-parallel Monte Carlo code ERO2.0 for plasma-wall interaction and 3D local impurity transport at JET ILW Open
Here, estimating erosion for plasma-facing components (PFCs) is one of the key issues for ITER. Effective sputter yields can be obtained experimentally e.g. by estimating flux ratios with S/XB ratios. The interpretation of such experiments…
View article: ERO2.0 modelling of the effects of surface roughness on molybdenum erosion and redeposition in the PSI-2 linear plasma device
ERO2.0 modelling of the effects of surface roughness on molybdenum erosion and redeposition in the PSI-2 linear plasma device Open
The surface morphology of plasma-facing components (PFCs) and its evolution during plasma irradiation has been shown to have a significant effect on the erosion and subsequent transport of sputtered particles in plasma. This in turn can in…
View article: First Monte‐Carlo modelling of global beryllium migration in ITER using ERO2.0
First Monte‐Carlo modelling of global beryllium migration in ITER using ERO2.0 Open
ERO2.0 is a recently developed Monte‐Carlo code for modelling global erosion and redeposition in fusion devices. We report here on the code's application to ITER for studying the erosion of the beryllium (Be) first wall armour under burnin…