Publikationen von H. Maier
Alle Typen
Vortrag (17)
41.
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)
42.
Vortrag
Progress in R&D on Plasma-Facing Materials and Components for Fusion Devices. aiv XXV Conference, Naples (eingereicht)
43.
Vortrag
Beneficial Deuterium Retention Properties of Tungsten Heavy Alloy. 15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS-15), Virtual (eingereicht)
44.
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)
45.
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)
46.
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)
47.
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)
48.
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)
49.
Vortrag
Potential approach of IR analysis for HHF quality assessment of ITER tungsten divertor targets. 22nd ITPA Meeting on SOL/Divertor Physics, Frascati (eingereicht)
50.
Vortrag
Potential approach of IR-analysis for HHF quality assessment of ITER tungsten divertor targets. 29th Symposium on Fusion Technology (SOFT 2016)
, Prague (eingereicht)
51.
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)
52.
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)
53.
Vortrag
Plasma-wall interaction in magnetic confinement fusion devices. Advances in Materials Development for Fusion Devices, Prague (eingereicht)
54.
Vortrag
Status and recent research at the neutral beam facility GLADIS. 5th International Workshop on Plasma Material Interaction Facilities for Fusion Research, Jülich (eingereicht)
55.
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)
56.
Vortrag
Impact of combined transient plasma/heat loads on tungsten performance. 21st International Conference on Plasma Surface Interactions 2014 (PSI 21), Kanazawa (2014)
57.
Vortrag
Erosion study of Fe-W binary mixed layer prepared as model system of RAFM steel. 21st International Conference on Plasma Surface Interactions 2014 (PSI 21), Kanazawa (eingereicht)
Poster (25)
58.
Poster
Qualification of W Heavy Alloys as Plasma Facing Material. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (eingereicht)
59.
Poster
Metallographic investigations of W-Ta- cold spray coatings on P92 after high heat flux loading. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (eingereicht)
60.
Poster
Deuterium retention in displacement-damaged selfpassivating tungsten alloys. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (eingereicht)