Publications of B. Böswirth
All genres
Journal Article (77)
21.
Journal Article
146, Pt. A, pp. 216 - 219 (2019)
Progress in high heat flux testing of European DEMO divertor mock-ups. Fusion Engineering and Design 22.
Journal Article
59, 112004 (2019)
Overview of first Wendelstein 7-X high-performance operation. Nuclear Fusion 23.
Journal Article
59, 112014 (2019)
Overview of physics studies on ASDEX Upgrade. Nuclear Fusion 24.
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 25.
Journal Article
146, Pt. A, pp. 417 - 420 (2019)
High heat-flux response of high-conductivity graphitic foam monoblocks. Fusion Engineering and Design 26.
Journal Article
46 (5), pp. 1398 - 1401 (2018)
Design and Test of Wendelstein 7-X Water-Cooled Divertor Scraper. IEEE Transactions on Plasma Science 27.
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 28.
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 29.
Journal Article
16, pp. 1 - 11 (2018)
European divertor target concepts for DEMO: Design rationales and high heat flux performance. Nuclear Materials and Energy 30.
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 31.
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 32.
Journal Article
T170, 014008 (2017)
Tungsten coating by ATC plasma spraying on CFC for WEST tokamak. Physica Scripta 33.
Journal Article
124, pp. 207 - 210 (2017)
Overview of the different processes of tungsten coating implemented into WEST tokamak. Fusion Engineering and Design 34.
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 35.
Journal Article
T170, 014001 (2017)
Results of high heat flux qualification tests of W monoblock components for WEST. Physica Scripta 36.
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 37.
Journal Article
12, pp. 1314 - 1318 (2017)
Irradiation effects of hydrogen and helium plasma on different grade tungsten materials. Nuclear Materials and Energy 38.
Journal Article
T170, 014022 (2017)
Realization of high heat flux tungsten monoblock type target with graded interlayer for application to DEMO divertor. Physica Scripta 39.
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 40.
Journal Article
T167, 014048 (2016)
Kinetics of carbide formation in the molybdenum-tungsten coatings used in the ITER-like Wall. Physica Scripta