Publications of M. Balden
All genres
Journal Article (224)
21.
Journal Article
61, 116006 (2021)
Gross and net erosion balance of plasma-facing materials in full-W tokamaks. Nuclear Fusion 22.
Journal Article
167, 112385 (2021)
A hot steam leak during baking of ASDEX Upgrade – Consequences and lessons learned. Fusion Engineering and Design 23.
Journal Article
27, 100972 (2021)
Deuterium retention in tungsten fiber-reinforced tungsten composites. Nuclear Materials and Energy 24.
Journal Article
555, 153135 (2021)
Influence of surface roughness on the sputter yield of Mo under keV D ion irradiation. Journal of Nuclear Materials 25.
Journal Article
96, 124035 (2021)
First post-mortem analysis of deposits collected on ITER-like components in WEST after the C3 and C4 campaigns. Physica Scripta 26.
Journal Article
96, 124070 (2021)
Erosion of tungsten marker layers in W7-X. Physica Scripta 27.
Journal Article
61, 116045 (2021)
Combined high fluence and high cycle number transient loading of ITER-like monoblocks in Magnum-PSI. Nuclear Fusion 28.
Journal Article
29, 101083 (2021)
Arc behaviour on different materials in ASDEX Upgrade. Nuclear Materials and Energy 29.
Journal Article
160, 111874 (2020)
Corrosion tests of multi-layer ceramic coatings in liquid lithium-lead. Fusion Engineering and Design 30.
Journal Article
23, 100749 (2020)
Impact of surface enrichment and morphology on sputtering of EUROFER by deuterium. Nuclear Materials and Energy 31.
Journal Article
2020 (T171), 014026 (2020)
Scanning electron microscopy analyses of an ITER plasma-facing unit mockup exposed to extreme ion fluences in Magnum-PSI. Physica Scripta 32.
Journal Article
2020 (T171), 014033 (2020)
Inspection of W 7-X plasma-facing components after the operation phase OP1.2b: observations and first assessments. Physica Scripta 33.
Journal Article
25, 100863 (2020)
ERO modelling of net and gross erosion of marker samples exposed to L-mode plasmas on ASDEX Upgrade. Nuclear Materials and Energy 34.
Journal Article
2020 (T171), 014050 (2020)
Helium irradiation effects on the surface modification and recrystallization of tungsten. Physica Scripta 35.
Journal Article
2020 (T171), 014037 (2020)
Impact of H-mode plasma operation on pre-damaged tungsten divertor tiles in ASDEX Upgrade. Physica Scripta 36.
Journal Article
60, 106007 (2020)
Deuterium retention in solid and liquid tin after low-temperature plasma exposure. Nuclear Fusion 37.
Journal Article
2020 (T171), 014035 (2020)
Material erosion and deposition on the divertor of W7-X. Physica Scripta 38.
Journal Article
2020 (T171), 014065 (2020)
ITER monoblock performance under lifetime loading conditions in Magnum-PSI. Physica Scripta 39.
Journal Article
157, 111630 (2020)
Recovery from a hot water leakage at the tokamak ASDEX upgrade. Fusion Engineering and Design 40.
Journal Article
88, 105189 (2020)
Evaluating crystal-orientation-dependent properties on polycrystalline tungsten: Example oxidation. International Journal of Refractory Metals and Hard Materials