K. Schmid
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View article: Application of an improved WallDYN surface model to estimate ITER boronization layer lifetime
Application of an improved WallDYN surface model to estimate ITER boronization layer lifetime Open
The WallDYN code was developed to model the coupled evolution of the impurity influx onto the first wall, the surface composition and the flux of impurities back into the plasma in fusion devices. It was recently shown that its default sur…
View article: The new ITER baseline, research plan and open R&D issues
The new ITER baseline, research plan and open R&D issues Open
A new baseline (NB) has been proposed by the ITER Project to ensure a robust achievement of the Projects’ goals, in view of past challenges including delays incurred due to the Covid-19 pandemic, technical challenges in completing first-of…
View article: Evaluating remote sensing data as a tool to minimize spatial autocorrelation in in-situ vegetation sampling
Evaluating remote sensing data as a tool to minimize spatial autocorrelation in in-situ vegetation sampling Open
The distinction between geographical patterns caused by underlying environmental factors and inherent spatial autocorrelation is a general challenge for field research. The quality and validity of phytogeographical studies is strongly depe…
View article: Scrape-off layer and divertor physics: Chapter 5 of the special issue: on the path to tokamak burning plasma operation
Scrape-off layer and divertor physics: Chapter 5 of the special issue: on the path to tokamak burning plasma operation Open
Since the publication of the review Progress in the ITER Physics Basis (PIPB) in 2007, significant progress has been made in understanding the processes at the plasma-material interface. This review, part of the ITPA Nuclear Fusion Special…
View article: Re-evaluation of the impact of wall retention on Tritium-self-sufficiency in fusion reactors
Re-evaluation of the impact of wall retention on Tritium-self-sufficiency in fusion reactors Open
In recent years several publications have claimed that the retention of tritium (T) in the first wall armor material poses a limitation on when a fusion reactor becomes T-self-sufficient. While the prediction on wall retention therein are …
View article: Thermal helium beam diagnostic for 2D profile measurements in the divertor of ASDEX Upgrade
Thermal helium beam diagnostic for 2D profile measurements in the divertor of ASDEX Upgrade Open
A new thermal helium beam diagnostic has been implemented in the outer lower divertor of the ASDEX Upgrade tokamak. The purpose of this diagnostic is to measure two-dimensional profiles of electron density (ne) and temperature (Te) with hi…
View article: Full W ITER: Assessment of expected W erosion and implications of boronization on fuel retention
Full W ITER: Assessment of expected W erosion and implications of boronization on fuel retention Open
Substituting Beryllium (Be) with Tungsten (W) as material for the first wall gives rise to new challenges for the ITER project. The additional W at the main chamber could result in a significant influx of high-Z impurities into the plasma …
View article: An integral approach to plasma-wall interaction modelling for EU-DEMO
An integral approach to plasma-wall interaction modelling for EU-DEMO Open
An integral approach to plasma-wall interaction (PWI) modelling for DEMO is presented, which is part of the EUROfusion Theory and Advanced Simulation Coordination activities that were established to advance the understanding and predictive…
View article: Integrated modeling of boron powder injection for real-time plasma-facing component conditioning
Integrated modeling of boron powder injection for real-time plasma-facing component conditioning Open
An integrated modeling framework for investigating the application of solid boron powder injection for real-time surface conditioning of plasma-facing components in tokamak environments is presented. Utilizing the DIII-D impurity powder dr…
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: Implications of T loss in first wall armor and structural materials on T-self-sufficiency in future burning fusion devices
Implications of T loss in first wall armor and structural materials on T-self-sufficiency in future burning fusion devices Open
Future fusion reactors will have to breed enough tritium (T) to sustain continuous operation and to produce excess T to power up other fusion reactors. Therefore, T is a scarce resource that must not be lost inside the fusion power plants …
View article: What You Use is What You Get: Unforced Errors in Studying Cultural Aspects in Agile Software Development
What You Use is What You Get: Unforced Errors in Studying Cultural Aspects in Agile Software Development Open
Context: Cultural aspects are of high importance as they guide people's behaviour and thus, influence how people apply methods and act in projects. In recent years, software engineering research emphasized the need to analyze the challenge…
View article: On the factors enhancing hydrogen trapping in spherical cavities in metals
On the factors enhancing hydrogen trapping in spherical cavities in metals Open
Using the reaction–diffusion model for hydrogen (H) trapping in spherical cavities in metals (Zibrov and Schmid, 2022), we theoretically analyze the case of H trapping only in chemisorption sites at the cavity surface. We show that the mod…
View article: Annealing of hydrogen trap sites in displacement-damaged EUROFER
Annealing of hydrogen trap sites in displacement-damaged EUROFER Open
For future fusion power plants, the reduced activation ferritic/martensitic (RAFM) steel EUROFER is considered to be the primary choice as a structural material for plasma facing components (PFC) of the first wall, such as the blanket modu…
View article: Investigation of helium exhaust dynamics at the ASDEX Upgrade tokamak with full-tungsten wall
Investigation of helium exhaust dynamics at the ASDEX Upgrade tokamak with full-tungsten wall Open
An efficient removal of He ash by active pumping in future fusion devices is necessary to avoid fuel dilution and not degrade the core confinement properties. Therefore, a deep understanding of the underlying physics mechanisms is mandator…
View article: Characterizing The Impact of Culture on Agile Methods: The MoCA Model
Characterizing The Impact of Culture on Agile Methods: The MoCA Model Open
Agile methods are well-known approaches in software development and used in various settings, which may vary wrt. organizational size, culture, or industrial sector. One important facet for the successful use of agile methods is the strong…
View article: Influence of hydrogen isotopes on displacement damage formation in EUROFER
Influence of hydrogen isotopes on displacement damage formation in EUROFER Open
The reduced activation ferritic martensitic steel EUROFER is one of the foreseen structural materials for future fusion reactors. The exposure to energetic fusion neutrons will generate displacement damage in the steel which acts as trappi…
View article: Preliminary assessment of tritium permeation and retention in the European Water Cooled Lithium Lead Test Blanket Module with TESSIM-X
Preliminary assessment of tritium permeation and retention in the European Water Cooled Lithium Lead Test Blanket Module with TESSIM-X Open
Tritium self-sufficiency is a key requirement for future fusion power plants. Therefore, it will be necessary to minimize tritium losses to the surrounding systems, such as the tritium breeding modules, plasma-facing components, cooling sy…
View article: Reaction–diffusion simulations of hydrogen isotope trapping and release from cavities in tungsten, II: Array of cavities
Reaction–diffusion simulations of hydrogen isotope trapping and release from cavities in tungsten, II: Array of cavities Open
We present a reaction–diffusion model of hydrogen (H) trapping and release from a metal containing an array of cavities. The model is based on a kinetic description of H trapping in chemisorption sites at the cavity surface and H2 gas prec…
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: Comparison of the influence of 2D and 3D geometry of the main chamber on plasma parameters in the SOL of ASDEX Upgrade
Comparison of the influence of 2D and 3D geometry of the main chamber on plasma parameters in the SOL of ASDEX Upgrade Open
In this paper the influence of toroidally asymmetric wall features on plasma solutions for ASDEX Upgrade is investigated by using the 3D scrape-off-layer simulation code EMC3-EIRENE. A comparison of simulation results in a 2D case with a t…
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: Plasma–surface interaction in the stellarator W7-X: conclusions drawn from operation with graphite plasma-facing components
Plasma–surface interaction in the stellarator W7-X: conclusions drawn from operation with graphite plasma-facing components Open
W7-X completed its plasma operation in hydrogen with island divertor and inertially cooled test divertor unit (TDU) made of graphite. A substantial set of plasma-facing components (PFCs), including in particular marker target elements, wer…