Publikationen von H. Greuner
Alle Typen
Zeitschriftenartikel (196)
61.
Zeitschriftenartikel
46 (5), S. 1398 - 1401 (2018)
Design and Test of Wendelstein 7-X Water-Cooled Divertor Scraper. IEEE Transactions on Plasma Science 62.
Zeitschriftenartikel
136, Pt. A, S. 558 - 562 (2018)
FEM and thermal fatigue testing comparison of ITER-like divertor PFUs mock-ups for DEMO. Fusion Engineering and Design 63.
Zeitschriftenartikel
134 (1), S. 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.
Zeitschriftenartikel
511, S. 567 - 573 (2018)
Results on the use of tungsten heavy alloys in the divertor of ASDEX Upgrade. Journal of Nuclear Materials 65.
Zeitschriftenartikel
136, Pt. B, S. 1593 - 1596 (2018)
Manufacturing and testing of ITER-like divertor plasma facing mock-ups for DEMO. Fusion Engineering and Design 66.
Zeitschriftenartikel
58, 096001 (2018)
Surface modification of W–V alloy exposed to high heat flux helium neutral beams. Nuclear Fusion 67.
Zeitschriftenartikel
16, S. 1 - 11 (2018)
European divertor target concepts for DEMO: Design rationales and high heat flux performance. Nuclear Materials and Energy 68.
Zeitschriftenartikel
136, Pt. B, S. 1052 - 1057 (2018)
Cracks avoidance with a modified solid tungsten divertor in ASDEX Upgrade. Fusion Engineering and Design 69.
Zeitschriftenartikel
T170, 014074 (2017)
Experimental results of near real-time protection system for plasma facing components in Wendelstein 7-X at GLADIS. Physica Scripta 70.
Zeitschriftenartikel
13, S. 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.
Zeitschriftenartikel
124, S. 348 - 351 (2017)
Summary of the production of the divertor target elements of Wendelstein 7-X. Fusion Engineering and Design 72.
Zeitschriftenartikel
57, 116041 (2017)
Plasma-wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification. Nuclear Fusion 73.
Zeitschriftenartikel
12, S. 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.
Zeitschriftenartikel
121, S. 211 - 217 (2017)
Thermal-hydraulics modeling for prototype testing of the W7-X high heat flux scraper element. Fusion Engineering and Design 75.
Zeitschriftenartikel
124, S. 432 - 436 (2017)
ITER-like divertor target for DEMO: Design study and fabrication test. Fusion Engineering and Design 76.
Zeitschriftenartikel
T170, 014008 (2017)
Tungsten coating by ATC plasma spraying on CFC for WEST tokamak. Physica Scripta 77.
Zeitschriftenartikel
124, S. 207 - 210 (2017)
Overview of the different processes of tungsten coating implemented into WEST tokamak. Fusion Engineering and Design 78.
Zeitschriftenartikel
T170, 014029 (2017)
High heat flux testing of mm thick tungsten coatings on carbon-fiber composites for the JT-60SA tokamak. Physica Scripta 79.
Zeitschriftenartikel
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.
Zeitschriftenartikel
T170, 014001 (2017)
Results of high heat flux qualification tests of W monoblock components for WEST. Physica Scripta