Publications of H. Greuner
All genres
Journal Article (181)
2019
Journal Article
146, Pt. B, pp. 1657 - 1660 (2019)
High heat flux test results for a thermal break DEMO divertor target and subsequent design and manufacture development. Fusion Engineering and Design
Journal Article
59, 112014 (2019)
Overview of physics studies on ASDEX Upgrade. Nuclear Fusion
Journal Article
146, Pt. A, pp. 858 - 861 (2019)
Performance assessment of high heat flux W monoblock type target using thin graded and copper interlayers for application to DEMO divertor. Fusion Engineering and Design
Journal Article
146, Pt. A, pp. 417 - 420 (2019)
High heat-flux response of high-conductivity graphitic foam monoblocks. Fusion Engineering and Design
Journal Article
146, Pt. B, pp. 2434 - 2437 (2019)
Measures to overcome deep cracks of tungsten tiles in the ASDEX Upgrade divertor. Fusion Engineering and Design 2018
Journal Article
46 (5), pp. 1398 - 1401 (2018)
Design and Test of Wendelstein 7-X Water-Cooled Divertor Scraper. IEEE Transactions on Plasma Science
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
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
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
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
Journal Article
58, 096001 (2018)
Surface modification of W–V alloy exposed to high heat flux helium neutral beams. Nuclear Fusion
Journal Article
16, pp. 1 - 11 (2018)
European divertor target concepts for DEMO: Design rationales and high heat flux performance. Nuclear Materials and Energy
Journal Article
136, Pt. B, pp. 1052 - 1057 (2018)
Cracks avoidance with a modified solid tungsten divertor in ASDEX Upgrade. Fusion Engineering and Design 2017
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
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
Journal Article
124, pp. 348 - 351 (2017)
Summary of the production of the divertor target elements of Wendelstein 7-X. Fusion Engineering and Design
Journal Article
57, 116041 (2017)
Plasma-wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification. Nuclear Fusion
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
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
Journal Article
124, pp. 432 - 436 (2017)
ITER-like divertor target for DEMO: Design study and fabrication test. Fusion Engineering and Design