Publikationen von H. Maier
Alle Typen
Zeitschriftenartikel (42)
41.
Zeitschriftenartikel
266, S. 1003 - 1008 (1999)
Erosion and deposition in the ASDEX Upgrade tungsten divertor experiment. Journal of Nuclear Materials 42.
Zeitschriftenartikel
266-269, S. 1296 - 1302 (1999)
Hydrogen isotope inventories in the ASDEX-Upgrade tungsten coated divertor tiles. Journal of Nuclear Materials Konferenzbeitrag (1)
43.
Konferenzbeitrag
455 (1-3), S. 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, 20. Oktober 2013 - 26. Oktober 2013. Journal of Nuclear Materials Vortrag (18)
44.
Vortrag
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 (eingereicht)
45.
Vortrag
Hydrogen and Deuterium Migration in Zirconium Oxide Coating by Gamma-ray Irradiation. 18th International Conference on Diffusion in Solids and Liquids (DSL 2022), Florence (eingereicht)
46.
Vortrag
Progress in R&D on Plasma-Facing Materials and Components for Fusion Devices. aiv XXV Conference, Naples (eingereicht)
47.
Vortrag
Beneficial Deuterium Retention Properties of Tungsten Heavy Alloy. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (eingereicht)
48.
Vortrag
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)
49.
Vortrag
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 (eingereicht)
50.
Vortrag
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 (eingereicht)
51.
Vortrag
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)
52.
Vortrag
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 (eingereicht)
53.
Vortrag
Potential approach of IR analysis for HHF quality assessment of ITER tungsten divertor targets. 22nd ITPA Meeting on SOL/Divertor Physics, Frascati (eingereicht)
54.
Vortrag
Potential approach of IR-analysis for HHF quality assessment of ITER tungsten divertor targets. 29th Symposium on Fusion Technology (SOFT 2016)
, Prague (eingereicht)
55.
Vortrag
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 (eingereicht)
56.
Vortrag
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)
57.
Vortrag
Plasma-wall interaction in magnetic confinement fusion devices. Advances in Materials Development for Fusion Devices, Prague (eingereicht)
58.
Vortrag
Status and recent research at the neutral beam facility GLADIS. 5th International Workshop on Plasma Material Interaction Facilities for Fusion Research, Jülich (eingereicht)
59.
Vortrag
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 (eingereicht)
60.
Vortrag
Impact of combined transient plasma/heat loads on tungsten performance. 21st International Conference on Plasma Surface Interactions 2014 (PSI 21), Kanazawa (2014)