Publications of J. Boscary
All genres
Talk (36)
121.
Talk
Results and consequences of high heat flux testing as quality assessment of the Wendelstein 7-X divertor. 27th Symposium on Fusion Technology (SOFT 2012), Liège (2012)
122.
Talk
Design and Technological Solutions for the Plasma Facing Components of Wendelstein 7-X. 26th Symposium on Fusion Technology (SOFT 2010), Porto (2010)
123.
Talk
Steady-state in vessel components in Wendelstein 7-X stellarator. 18th International Toki Conference (ITC18), Ceratopia Toki, Toki Gifu (2008)
124.
Talk
Status of the in-vessel components of the experiment W7-X. 25th Symposium on Fusion Technology (SOFT 2008), Rostock (2008)
125.
Talk
Cyclic Heat Load Testing of Improved CFC/Cu Bonding for the W7-X Divertor Targets. 13th International Conference on Fusion Reactor Materials (ICFRM-13), Nice (2007)
126.
Talk
Testing of improved CFC/Cu Bondings for the W7-X Divertor Targets. 13th International Conference on Fusion Reactor Materials (ICFRM-13), Nice (2007)
127.
Talk
Fabrication and testing of W7-X pre-series target elements. 11th International Workshop on Plasma-Facing Materials and Components for Fusion Applications (PFMC-11), Greifswald (2006)
128.
Talk
Status of the pre-series activities of the target elements for the W7-X divertor. ITER Divertor Meeting, St. Petersburg (2006)
129.
Talk
Highly heat-loaded plasma-facing components of Wendelstein 7-X. Congres Francais de Thermique, Ile de Re (2006)
130.
Talk
Recent testing in the GLADIS HHF test facility in Garching. ITER Divertor Meeting, St. Petersburg (2006)
131.
Talk
Examination of W7-X pre-series divertor target elements. International Workshop on Divertor Related Issues (Satellite Workshop PSI-17), Huangshan Mountain (2006)
132.
Talk
Materials for the Plasma-Facing Components of Steady State Stellarators. 15th International Stellarator Workshop, Madrid (2005)
133.
Talk
High Heat Flux Facility GLADIS - Operational Characteristics and Results of W7-X Pre-Series Target Tests. 12th International Conference on Fusion Reactor Materials (ICFRM-12), Santa Barbara,CA (2005)
134.
Talk
Physics, Technologies and Status of the Wendelstein 7-X Device. 20th IAEA Fusion Energy Conference, Vilamoura (2004)
135.
Talk
Modification of the Target Design of the W7-X Divertor for Steady-State Operation. 20th IEEE-NPSS Symposium on Fusion Engineering (SOFE), San Diego,CA (2003)
Poster (54)
136.
Poster
Galvanic process for infiltration of W fibre-reinforced heat sinks. 15th International Symposium on Fusion Nuclear Technology (ISFNT-15), Las Palmas de Gran Canaria (submitted)
137.
Poster
Thermal and structural analyses of an additive manufactured panel mock-up for Wendelstein 7-X. 15th International Symposium on Fusion Nuclear Technology (ISFNT-15), Las Palmas de Gran Canaria (submitted)
138.
Poster
Conceptual design of the next generation of W7-X divertor W-target elements. 32nd Symposium on Fusion Technology (SOFT 2022), Dubrovnik, Virtual (submitted)
139.
Poster
Numerical analysis of boiling effects in cooling channels of W7-X divertor target element. 32nd Symposium on Fusion Technology (SOFT 2022), Dubrovnik, Virtual (submitted)
140.
Poster
Thermal analysis of actively cooled divertor target element for stellarator W7-X. 30th International Conference Nuclear Energy for New Europe (NENE 2021), Bled (2021)