Publications of M. Balden
All genres
Journal Article (241)
41.
Journal Article
27, 100972 (2021)
Deuterium retention in tungsten fiber-reinforced tungsten composites. Nuclear Materials and Energy 42.
Journal Article
555, 153135 (2021)
Influence of surface roughness on the sputter yield of Mo under keV D ion irradiation. Journal of Nuclear Materials 43.
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 44.
Journal Article
96, 124070 (2021)
Erosion of tungsten marker layers in W7-X. Physica Scripta 45.
Journal Article
61, 116045 (2021)
Combined high fluence and high cycle number transient loading of ITER-like monoblocks in Magnum-PSI. Nuclear Fusion 46.
Journal Article
29, 101083 (2021)
Arc behaviour on different materials in ASDEX Upgrade. Nuclear Materials and Energy 47.
Journal Article
160, 111874 (2020)
Corrosion tests of multi-layer ceramic coatings in liquid lithium-lead. Fusion Engineering and Design 48.
Journal Article
23, 100749 (2020)
Impact of surface enrichment and morphology on sputtering of EUROFER by deuterium. Nuclear Materials and Energy 49.
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 50.
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 51.
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 52.
Journal Article
2020 (T171), 014050 (2020)
Helium irradiation effects on the surface modification and recrystallization of tungsten. Physica Scripta 53.
Journal Article
2020 (T171), 014037 (2020)
Impact of H-mode plasma operation on pre-damaged tungsten divertor tiles in ASDEX Upgrade. Physica Scripta 54.
Journal Article
60, 106007 (2020)
Deuterium retention in solid and liquid tin after low-temperature plasma exposure. Nuclear Fusion 55.
Journal Article
2020 (T171), 014035 (2020)
Material erosion and deposition on the divertor of W7-X. Physica Scripta 56.
Journal Article
2020 (T171), 014065 (2020)
ITER monoblock performance under lifetime loading conditions in Magnum-PSI. Physica Scripta 57.
Journal Article
157, 111630 (2020)
Recovery from a hot water leakage at the tokamak ASDEX upgrade. Fusion Engineering and Design 58.
Journal Article
88, 105189 (2020)
Evaluating crystal-orientation-dependent properties on polycrystalline tungsten: Example oxidation. International Journal of Refractory Metals and Hard Materials 59.
Journal Article
125, 225502 (2020)
Absence of a Crystal Direction Regime in which Sputtering Corresponds to Amorphous Material. Physical Review Letters 60.
Journal Article
146, Pt. A, pp. 242 - 245 (2019)
Erosion and deposition investigations on Wendelstein 7-X first wall components for the first operation phase in divertor configuration. Fusion Engineering and Design