Publications of H. Greuner
All genres
Journal Article (196)
61.
Journal Article
46 (5), pp. 1398 - 1401 (2018)
Design and Test of Wendelstein 7-X Water-Cooled Divertor Scraper. IEEE Transactions on Plasma Science 62.
Journal Article
136, Pt. A, pp. 558 - 562 (2018)
FEM and thermal fatigue testing comparison of ITER-like divertor PFUs mock-ups for DEMO. Fusion Engineering and Design 63.
Journal Article
134 (1), pp. 143 - 155 (2018)
Thermal analysis and high heat flux testing of unidirectional carbon–carbon composite for infrared imaging diagnostic. Journal of Thermal Analysis and Calorimetry 64.
Journal Article
511, pp. 567 - 573 (2018)
Results on the use of tungsten heavy alloys in the divertor of ASDEX Upgrade. Journal of Nuclear Materials 65.
Journal Article
136, Pt. B, pp. 1593 - 1596 (2018)
Manufacturing and testing of ITER-like divertor plasma facing mock-ups for DEMO. Fusion Engineering and Design 66.
Journal Article
58, 096001 (2018)
Surface modification of W–V alloy exposed to high heat flux helium neutral beams. Nuclear Fusion 67.
Journal Article
16, pp. 1 - 11 (2018)
European divertor target concepts for DEMO: Design rationales and high heat flux performance. Nuclear Materials and Energy 68.
Journal Article
136, Pt. B, pp. 1052 - 1057 (2018)
Cracks avoidance with a modified solid tungsten divertor in ASDEX Upgrade. Fusion Engineering and Design 69.
Journal Article
T170, 014074 (2017)
Experimental results of near real-time protection system for plasma facing components in Wendelstein 7-X at GLADIS. Physica Scripta 70.
Journal Article
13, pp. 74 - 80 (2017)
Microstructural stability of spark-plasma-sintered Wf/W composite with zirconia interface coating under high-heat-flux hydrogen beam irradiation. Nuclear Materials and Energy 71.
Journal Article
124, pp. 348 - 351 (2017)
Summary of the production of the divertor target elements of Wendelstein 7-X. Fusion Engineering and Design 72.
Journal Article
57, 116041 (2017)
Plasma-wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification. Nuclear Fusion 73.
Journal Article
12, pp. 575 - 581 (2017)
Surface modification of He pre-exposed tungsten samples by He plasma impact in the divertor manipulator of ASDEX Upgrade. Nuclear Materials and Energy 74.
Journal Article
121, pp. 211 - 217 (2017)
Thermal-hydraulics modeling for prototype testing of the W7-X high heat flux scraper element. Fusion Engineering and Design 75.
Journal Article
124, pp. 432 - 436 (2017)
ITER-like divertor target for DEMO: Design study and fabrication test. Fusion Engineering and Design 76.
Journal Article
T170, 014008 (2017)
Tungsten coating by ATC plasma spraying on CFC for WEST tokamak. Physica Scripta 77.
Journal Article
124, pp. 207 - 210 (2017)
Overview of the different processes of tungsten coating implemented into WEST tokamak. Fusion Engineering and Design 78.
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 79.
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 80.
Journal Article
T170, 014001 (2017)
Results of high heat flux qualification tests of W monoblock components for WEST. Physica Scripta