Publications of B. Böswirth
All genres
Journal Article (86)
41.
Journal Article
T170, 014008 (2017)
Tungsten coating by ATC plasma spraying on CFC for WEST tokamak. Physica Scripta 42.
Journal Article
124, pp. 207 - 210 (2017)
Overview of the different processes of tungsten coating implemented into WEST tokamak. Fusion Engineering and Design 43.
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 44.
Journal Article
T170, 014001 (2017)
Results of high heat flux qualification tests of W monoblock components for WEST. Physica Scripta 45.
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 46.
Journal Article
12, pp. 1314 - 1318 (2017)
Irradiation effects of hydrogen and helium plasma on different grade tungsten materials. Nuclear Materials and Energy 47.
Journal Article
T170, 014022 (2017)
Realization of high heat flux tungsten monoblock type target with graded interlayer for application to DEMO divertor. Physica Scripta 48.
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 49.
Journal Article
T167, 014048 (2016)
Kinetics of carbide formation in the molybdenum-tungsten coatings used in the ITER-like Wall. Physica Scripta 50.
Journal Article
87, 02B126 (2016)
Development and tests of molybdenum armored copper components for MITICA ion source. Review of Scientific Instruments 51.
Journal Article
98-99, pp. 1310 - 1313 (2015)
Results of high heat flux testing of W/CuCrZr multilayer composites with percolating microstructure for plasma-facing components. Fusion Engineering and Design 52.
Journal Article
98-99, pp. 1333 - 1336 (2015)
Results of high heat flux tests and structural analysis of the new solid tungsten divertor tile for ASDEX Upgrade. Fusion Engineering and Design 53.
Journal Article
463, pp. 223 - 227 (2015)
Surface modifications of W divertor components for EAST during exposure to high heat loads with He. Journal of Nuclear Materials 54.
Journal Article
466, pp. 357 - 361 (2015)
Micro- and nano-scale damage on the surface of W divertor component during exposure to high heat flux loads with He. Journal of Nuclear Materials 55.
Journal Article
463, pp. 337 - 340 (2015)
Determination of the temperature dependence of tungsten erosion. Journal of Nuclear Materials 56.
Journal Article
T159, 014003 (2014)
Experimental determination of the transient heat absorption of W divertor materials. Physica Scripta 57.
Journal Article
T159, 014019 (2014)
Tungsten erosion under combined hydrogen/helium high heat flux loading. Physica Scripta 58.
Journal Article
54, 083026 (2014)
Suppression of cavitation in melted tungsten by doping with lanthanum oxide. Nuclear Fusion 59.
Journal Article
442 (1-3), pp. S256 - S260 (2013)
Investigation of European tungsten materials exposed to high heat flux H/He neutral beams. Journal of Nuclear Materials 60.
Journal Article
88 (6-8), pp. 581 - 584 (2013)
Results and consequences of high heat flux testing as quality assessment of the Wendelstein 7-X divertor. Fusion Engineering and Design