Publications of H Maier
All genres
Journal Article (43)
41.
Journal Article
313-316, pp. 116 - 126 (2003)
New results from the tungsten programme at ASDEX Upgrade. Journal of Nuclear Materials 42.
Journal Article
266, pp. 1003 - 1008 (1999)
Erosion and deposition in the ASDEX Upgrade tungsten divertor experiment. Journal of Nuclear Materials 43.
Journal Article
266-269, pp. 1296 - 1302 (1999)
Hydrogen isotope inventories in the ASDEX-Upgrade tungsten coated divertor tiles. Journal of Nuclear Materials Conference Paper (1)
44.
Conference Paper
455 (1-3), pp. 681 - 684 (2014)
Surface morphology changes of tungsten exposed to high heat loading with mixed hydrogen/helium beams. 16th International Conference of Fusion Reactor Materials (ICFRM-16), Beijing, October 20, 2013 - October 26, 2013. Journal of Nuclear Materials Talk (18)
45.
Talk
Testing of tungsten fibre-reinforced tungsten composites at the neutral beam facility GLADIS. 8th International Workshop on Plasma Material Interaction Facilities for Fusion Research, Eindhoven (submitted)
46.
Talk
Hydrogen and Deuterium Migration in Zirconium Oxide Coating by Gamma-ray Irradiation. 18th International Conference on Diffusion in Solids and Liquids (DSL 2022), Florence (submitted)
47.
Talk
Progress in R&D on Plasma-Facing Materials and Components for Fusion Devices. aiv XXV Conference, Naples (submitted)
48.
Talk
Beneficial Deuterium Retention Properties of Tungsten Heavy Alloy. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (submitted)
49.
Talk
Current status of the development of oxidation-resistant tungsten-based alloys for first wall application in fusion devices. 19th International Conference on Fusion Reactor Materials (ICFRM-19), La Jolla, CA (2019)
50.
Talk
Gamma-ray irradiation effect on deuterium retention in reduced activation ferritic/martensitic steel and ceramic coatings. 19th International Conference on Fusion Reactor Materials (ICFRM-19), La Jolla, CA (submitted)
51.
Talk
Behaviour of mm-thick W coatings on CFC for JT-60SA under high heat fluxes. 16th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-16), Neuss (submitted)
52.
Talk
Status and recent research at the neutral beam facility GLADIS. 6th International Workshop on Plasma Material Interaction Facilities for Fusion Research (PMIF 2017), Tsukuba (2017)
53.
Talk
First Results on the Use of Tungsten Heavy Alloys in the Divertor of ASDEX Upgrade. 18th International Conference on Fusion Reactor Materials (ICFRM-18), Aomori (submitted)
54.
Talk
Potential approach of IR analysis for HHF quality assessment of ITER tungsten divertor targets. 22nd ITPA Meeting on SOL/Divertor Physics, Frascati (submitted)
55.
Talk
Potential approach of IR-analysis for HHF quality assessment of ITER tungsten divertor targets. 29th Symposium on Fusion Technology (SOFT 2016)
, Prague (submitted)
56.
Talk
Completion of W7-X divertor target manufacturing – Review of HHF testing strategy as quality assessment. 15th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-15), Aix-en-Provence (submitted)
57.
Talk
Thermal shock behaviour of H and H/He-exposed tungsten at high temperature. 15th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-15), Aix-en-Provence (2015)
58.
Talk
Plasma-wall interaction in magnetic confinement fusion devices. Advances in Materials Development for Fusion Devices, Prague (submitted)
59.
Talk
Status and recent research at the neutral beam facility GLADIS. 5th International Workshop on Plasma Material Interaction Facilities for Fusion Research, Jülich (submitted)
60.
Talk
Melt damage to the JET ITER-like Wall and divertor. 15th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-15), Aix-en-Provence (submitted)