Publications of K. Schmid
All genres
Journal Article (122)
1.
Journal Article
62, 026020 (2022)
Comparison of the influence of 2D and 3D geometry of the main chamber on plasma parameters in the SOL of ASDEX Upgrade. Nuclear Fusion 2.
Journal Article
62, 016006 (2022)
Plasma-surface interaction in the stellarator W7-X: conclusions drawn from operation with graphite plasma-facing components. Nuclear Fusion 3.
Journal Article
62, 042013 (2022)
Latest results of Eurofusion plasma-facing components research in the areas of power loading, material erosion and fuel retention. Nuclear Fusion 4.
Journal Article
62, 036011 (2022)
Beryllium erosion and redeposition in ITER H, He and D-T discharges. Nuclear Fusion 5.
Journal Article
62, 042006 (2022)
Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development. Nuclear Fusion 6.
Journal Article
30, 101121 (2022)
Reaction-diffusion simulations of hydrogen isotope trapping and release from cavities in tungsten, I: Single cavity. Nuclear Materials and Energy 7.
Journal Article
28, 101039 (2021)
Preliminary estimates of tritium permeation and retention in the first wall of DEMO due to ion bombardment. Nuclear Materials and Energy 8.
Journal Article
96, 124059 (2021)
Plasma-wall interaction studies in W7-X: main results from the recent divertor operations. Physica Scripta 9.
Journal Article
61, 086008 (2021)
On the use of recombination rate coefficients in hydrogen transport calculations. Nuclear Fusion 10.
Journal Article
2020 (T171), 014057 (2020)
ERO2.0 modelling of the effects of surface roughness on molybdenum erosion and redeposition in the PSI-2 linear plasma device. Physica Scripta 11.
Journal Article
25, 100821 (2020)
Integrated modelling: Coupling of surface evolution and plasma-impurity transport. Nuclear Materials and Energy 12.
Journal Article
2020 (T171), 014006 (2020)
Code/Code comparison of impurity transport in EMC3 and DIVIMP. Physica Scripta 13.
Journal Article
18, pp. 56 - 61 (2019)
Implications of PMI and wall material choice on fusion reactor tritium self-sufficiency. Nuclear Materials and Energy 14.
Journal Article
59, 056023 (2019)
High-flux hydrogen irradiation-induced cracking of tungsten reproduced by low-flux plasma exposure. Nuclear Fusion 15.
Journal Article
4 (1), 29 (2019)
Impact of Surface Roughness on Ion-Surface Interactions Studied with Energetic Carbon Ions 13C+ on Tungsten Surfaces. Condensed Matter 16.
Journal Article
59, 112021 (2019)
Overview of the JET preparation for deuterium-tritium operation with the ITER like-wall. Nuclear Fusion 17.
Journal Article
20, 100674 (2019)
WallDYN simulations of material migration and fuel retention in ITER low power H plasmas and high power neon-seeded DT plasmas. Nuclear Materials and Energy 18.
Journal Article
59, 112014 (2019)
Overview of physics studies on ASDEX Upgrade. Nuclear Fusion 19.
Journal Article
19, pp. 445 - 450 (2019)
Global modeling of wall material migration following boronization in NSTX-U. Nuclear Materials and Energy 20.
Journal Article
89, 103501 (2018)
SIESTA: A high current ion source for erosion and retention studies. Review of Scientific Instruments