Publikationen von J. Boscary
Alle Typen
Vortrag (36)
121.
Vortrag
Status of the in-vessel components of the experiment W7-X. 25th Symposium on Fusion Technology (SOFT 2008), Rostock (2008)
122.
Vortrag
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)
123.
Vortrag
Testing of improved CFC/Cu Bondings for the W7-X Divertor Targets. 13th International Conference on Fusion Reactor Materials (ICFRM-13), Nice (2007)
124.
Vortrag
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)
125.
Vortrag
Status of the pre-series activities of the target elements for the W7-X divertor. ITER Divertor Meeting, St. Petersburg (2006)
126.
Vortrag
Highly heat-loaded plasma-facing components of Wendelstein 7-X. Congres Francais de Thermique, Ile de Re (2006)
127.
Vortrag
Recent testing in the GLADIS HHF test facility in Garching. ITER Divertor Meeting, St. Petersburg (2006)
128.
Vortrag
Examination of W7-X pre-series divertor target elements. International Workshop on Divertor Related Issues (Satellite Workshop PSI-17), Huangshan Mountain (2006)
129.
Vortrag
Materials for the Plasma-Facing Components of Steady State Stellarators. 15th International Stellarator Workshop, Madrid (2005)
130.
Vortrag
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)
131.
Vortrag
Physics, Technologies and Status of the Wendelstein 7-X Device. 20th IAEA Fusion Energy Conference, Vilamoura (2004)
132.
Vortrag
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)
133.
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 (eingereicht)
134.
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 (eingereicht)
135.
Poster
Conceptual design of the next generation of W7-X divertor W-target elements. 32nd Symposium on Fusion Technology (SOFT 2022), Dubrovnik, Virtual (eingereicht)
136.
Poster
Numerical analysis of boiling effects in cooling channels of W7-X divertor target element. 32nd Symposium on Fusion Technology (SOFT 2022), Dubrovnik, Virtual (eingereicht)
137.
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)
138.
Poster
Completion of the production of the W7-X divertor target modules. 31st Symposium on Fusion Technology (SOFT 2020), Virtual Edition (eingereicht)
139.
Poster
Thermal loading test of a Wendelstein 7-X pumping gap panel. 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-18), Virtual (eingereicht)
140.
Poster
Progress in the production of the W7-X divertor target modules. 30th Symposium on Fusion Technology (SOFT 2018), Giardini Naxos (eingereicht)