Publications of H. Greuner
All genres
Journal Article (181)
61.
Journal Article
T170, 014008 (2017)
Tungsten coating by ATC plasma spraying on CFC for WEST tokamak. Physica Scripta 62.
Journal Article
124, pp. 207 - 210 (2017)
Overview of the different processes of tungsten coating implemented into WEST tokamak. Fusion Engineering and Design 63.
Journal Article
T170, 014029 (2017)
High heat flux testing of mm thick tungsten coatings on carbon-fiber composites for the JT-60SA tokamak. Physica Scripta 64.
Journal Article
T170, 014042 (2017)
The development and testing of the thermal break divertor monoblock target design delivering 20 MW m-2 heat load capability. Physica Scripta 65.
Journal Article
T170, 014001 (2017)
Results of high heat flux qualification tests of W monoblock components for WEST. Physica Scripta 66.
Journal Article
124, pp. 202 - 206 (2017)
Potential approach of IR-analysis for high heat flux quality assessment of divertor tungsten monoblock components. Fusion Engineering and Design 67.
Journal Article
57, 066015 (2017)
Plasma-wall interaction studies in the full-W ASDEX upgrade during helium plasma discharges. Nuclear Fusion 68.
Journal Article
12, pp. 205 - 209 (2017)
Experiences with a solid tungsten divertor in ASDEX Upgrade. Nuclear Materials and Energy 69.
Journal Article
57, 092012 (2017)
Material testing facilities and programs for plasma-facing component testing. Nuclear Fusion 70.
Journal Article
57, 102001 (2017)
Overview of the JET results in support to ITER. Nuclear Fusion 71.
Journal Article
12, pp. 1314 - 1318 (2017)
Irradiation effects of hydrogen and helium plasma on different grade tungsten materials. Nuclear Materials and Energy 72.
Journal Article
124, pp. 450 - 454 (2017)
Investigations on tungsten heavy alloys for use as plasma facing material. Fusion Engineering and Design 73.
Journal Article
69, pp. 66 - 109 (2017)
Ductilisation of tungsten (W): Tungsten laminated composites. International Journal of Refractory Metals and Hard Materials 74.
Journal Article
T170, 014022 (2017)
Realization of high heat flux tungsten monoblock type target with graded interlayer for application to DEMO divertor. Physica Scripta 75.
Journal Article
109-111, Pt. A, pp. 773 - 776 (2016)
Prototyping phase of the high heat flux scraper element of Wendelstein 7-X. Fusion Engineering and Design 76.
Journal Article
9, pp. 422 - 429 (2016)
Manufacturing and testing of self-passivating tungsten alloys of different composition. Nuclear Materials and Energy 77.
Journal Article
T167, 014012 (2016)
Operational limits on WEST inertial divertor sector during the early phase experiment. Physica Scripta 78.
Journal Article
109-111, Pt. A, pp. 169 - 174 (2016)
H/He irradiation on tungsten exposed to ELM-like thermal shocks. Fusion Engineering and Design 79.
Journal Article
T167, 014008 (2016)
Thermal shock behaviour of H and H/He-exposed tungsten at high temperature. Physica Scripta 80.
Journal Article
T167, 014048 (2016)
Kinetics of carbide formation in the molybdenum-tungsten coatings used in the ITER-like Wall. Physica Scripta