Publikationen von B. Böswirth
Alle Typen
Zeitschriftenartikel (87)
21.
Zeitschriftenartikel
175, 113010 (2022)
Divertor of the European DEMO: Engineering and technologies for power exhaust. Fusion Engineering and Design 22.
Zeitschriftenartikel
96, 124029 (2021)
Acceptance tests of the industrial series manufacturing of WEST ITER-like tungsten actively cooled divertor. Physica Scripta 23.
Zeitschriftenartikel
544, 152670 (2021)
High-heat-flux technologies for the European demo divertor targets: State-of-the-art and a review of the latest testing campaign. Journal of Nuclear Materials 24.
Zeitschriftenartikel
48 (6), S. 1519 - 1524 (2020)
Transient Computational and Experimental Thermal Analysis of Graphite Foam Monoblock. IEEE Transactions on Plasma Science 25.
Zeitschriftenartikel
2020 (T171), 014003 (2020)
Assessment of the high heat flux performance of European DEMO divertor mock-ups. Physica Scripta 26.
Zeitschriftenartikel
2020 (T171), 014037 (2020)
Impact of H-mode plasma operation on pre-damaged tungsten divertor tiles in ASDEX Upgrade. Physica Scripta 27.
Zeitschriftenartikel
2020 (T171), 014015 (2020)
Application of tungsten–copper composite heat sink materials to plasma-facing component mock-ups. Physica Scripta 28.
Zeitschriftenartikel
157, 111610 (2020)
Performance assessment of thick W/Cu graded interlayer for DEMO divertor target. Fusion Engineering and Design 29.
Zeitschriftenartikel
20, 100688 (2019)
Manufacturing, high heat flux testing and post mortem analyses of a W-PIM mock-up. Nuclear Materials and Energy 30.
Zeitschriftenartikel
516, S. 178 - 184 (2019)
Synergistic effects of ELMs and H–He irradiation on the degradation behavior of tungsten treated with high-energy-rate forging. Journal of Nuclear Materials 31.
Zeitschriftenartikel
146, Pt. A, S. 216 - 219 (2019)
Progress in high heat flux testing of European DEMO divertor mock-ups. Fusion Engineering and Design 32.
Zeitschriftenartikel
59, 112004 (2019)
Overview of first Wendelstein 7-X high-performance operation. Nuclear Fusion 33.
Zeitschriftenartikel
59, 112014 (2019)
Overview of physics studies on ASDEX Upgrade. Nuclear Fusion 34.
Zeitschriftenartikel
146, Pt. A, S. 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 35.
Zeitschriftenartikel
146, Pt. A, S. 417 - 420 (2019)
High heat-flux response of high-conductivity graphitic foam monoblocks. Fusion Engineering and Design 36.
Zeitschriftenartikel
46 (5), S. 1398 - 1401 (2018)
Design and Test of Wendelstein 7-X Water-Cooled Divertor Scraper. IEEE Transactions on Plasma Science 37.
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 38.
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 39.
Zeitschriftenartikel
16, S. 1 - 11 (2018)
European divertor target concepts for DEMO: Design rationales and high heat flux performance. Nuclear Materials and Energy 40.
Zeitschriftenartikel
T170, 014074 (2017)
Experimental results of near real-time protection system for plasma facing components in Wendelstein 7-X at GLADIS. Physica Scripta