Publikationen von J. Boscary
Alle Typen
Zeitschriftenartikel (83)
1.
Zeitschriftenartikel
212, 114861 (2025)
Divertor conceptual design of the European Volumetric Neutron Source. Fusion Engineering and Design 2.
Zeitschriftenartikel
201, 114268 (2024)
Galvanic process for Cu-infiltration of W fibre-reinforced heat sinks. Fusion Engineering and Design 3.
Zeitschriftenartikel
203, 114467 (2024)
Selection of EU-DEMO divertor operating conditions: water cooling thermal-hydraulic parameters and power exhaust capabilities. Fusion Engineering and Design 4.
Zeitschriftenartikel
204, 114495 (2024)
Thermal-hydraulic and structural analyses of an additive manufactured panel mock-up for Wendelstein 7-X. Fusion Engineering and Design 5.
Zeitschriftenartikel
192, 113629 (2023)
Conceptual design of the next generation of W7-X divertor W-target elements. Fusion Engineering and Design 6.
Zeitschriftenartikel
175, 112986 (2022)
Thermal loading test of a Wendelstein 7-X pumping gap panel. Fusion Engineering and Design 7.
Zeitschriftenartikel
62, 042022 (2022)
Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X. Nuclear Fusion 8.
Zeitschriftenartikel
166, 112293 (2021)
Completion of the production of the W7-X divertor target modules. Fusion Engineering and Design 9.
Zeitschriftenartikel
161, 111882 (2020)
Thermal and mechanical analyses of W7-X plasma facing components for operation phase 2. Fusion Engineering and Design 10.
Zeitschriftenartikel
146, Pt. B, S. 1975 - 1978 (2019)
Progress in the production of the W7-X divertor target modules. Fusion Engineering and Design 11.
Zeitschriftenartikel
146, Pt. B, S. 2757 - 2760 (2019)
Design and manufacturing of the Wendelstein 7-X cryo-vacuum pump. Fusion Engineering and Design 12.
Zeitschriftenartikel
146, Pt. A, S. 1166 - 1170 (2019)
Repair processes of Wendelstein 7-X target modules. Fusion Engineering and Design 13.
Zeitschriftenartikel
59, 112004 (2019)
Overview of first Wendelstein 7-X high-performance operation. Nuclear Fusion 14.
Zeitschriftenartikel
59, 066041 (2019)
Measurement and modeling of magnetic configurations to mimic overload scenarios in the W7-X stellarator. Nuclear Fusion 15.
Zeitschriftenartikel
46 (5), S. 1398 - 1401 (2018)
Design and Test of Wendelstein 7-X Water-Cooled Divertor Scraper. IEEE Transactions on Plasma Science 16.
Zeitschriftenartikel
46 (5), S. 1387 - 1392 (2018)
Modeling and Preparation for Experimental Testing of Heat Fluxes on W7-X Divertor Scraper Elements. IEEE Transactions on Plasma Science 17.
Zeitschriftenartikel
46 (5), S. 1576 - 1579 (2018)
Thermal and Mechanical Analysis of the Wendelstein 7-X Cryo-Vacuum Pump Plug-In. IEEE Transactions on Plasma Science 18.
Zeitschriftenartikel
124, S. 348 - 351 (2017)
Summary of the production of the divertor target elements of Wendelstein 7-X. Fusion Engineering and Design 19.
Zeitschriftenartikel
121, S. 211 - 217 (2017)
Thermal-hydraulics modeling for prototype testing of the W7-X high heat flux scraper element. Fusion Engineering and Design 20.
Zeitschriftenartikel
T170, 014045 (2017)
Examinations for leak tightness of actively cooled components in ITER and fusion devices. Physica Scripta