Publikationen von J. Boscary
Alle Typen
Zeitschriftenartikel (78)
1.
Zeitschriftenartikel
175, 112986 (2022)
Thermal loading test of a Wendelstein 7-X pumping gap panel. Fusion Engineering and Design 2.
Zeitschriftenartikel
166, 112293 (2021)
Completion of the production of the W7-X divertor target modules. Fusion Engineering and Design 3.
Zeitschriftenartikel
161, 111882 (2020)
Thermal and mechanical analyses of W7-X plasma facing components for operation phase 2. Fusion Engineering and Design 4.
Zeitschriftenartikel
146, Pt. B, S. 1975 - 1978 (2019)
Progress in the production of the W7-X divertor target modules. Fusion Engineering and Design 5.
Zeitschriftenartikel
146, Pt. B, S. 2757 - 2760 (2019)
Design and manufacturing of the Wendelstein 7-X cryo-vacuum pump. Fusion Engineering and Design 6.
Zeitschriftenartikel
146, Pt. A, S. 1166 - 1170 (2019)
Repair processes of Wendelstein 7-X target modules. Fusion Engineering and Design 7.
Zeitschriftenartikel
59, 112004 (2019)
Overview of first Wendelstein 7-X high-performance operation. Nuclear Fusion 8.
Zeitschriftenartikel
59, 066041 (2019)
Measurement and modeling of magnetic configurations to mimic overload scenarios in the W7-X stellarator. Nuclear Fusion 9.
Zeitschriftenartikel
46 (5), S. 1398 - 1401 (2018)
Design and Test of Wendelstein 7-X Water-Cooled Divertor Scraper. IEEE Transactions on Plasma Science 10.
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 11.
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 12.
Zeitschriftenartikel
124, S. 348 - 351 (2017)
Summary of the production of the divertor target elements of Wendelstein 7-X. Fusion Engineering and Design 13.
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 14.
Zeitschriftenartikel
T170, 014045 (2017)
Examinations for leak tightness of actively cooled components in ITER and fusion devices. Physica Scripta 15.
Zeitschriftenartikel
T170, 019601 (2017)
Erratum: Examinations for leak tightness of actively cooled components in ITER and fusion devices (2017 Phys. Scr. 2017 014045). Physica Scripta 16.
Zeitschriftenartikel
124, S. 483 - 486 (2017)
Local copper coating of the connectors of the divertor target elements of Wendelstein 7-X. Fusion Engineering and Design 17.
Zeitschriftenartikel
124, S. 292 - 296 (2017)
Structural analysis of the W7-X cryopump during the superconducting coil fast discharge event. Fusion Engineering and Design 18.
Zeitschriftenartikel
109-111, Pt. A, S. 773 - 776 (2016)
Prototyping phase of the high heat flux scraper element of Wendelstein 7-X. Fusion Engineering and Design 19.
Zeitschriftenartikel
44 (9, Part 1), S. 1738 - 1744 (2016)
Overview of Design and Analysis Activities for the W7-X Scraper Element. IEEE Transactions on Plasma Science 20.
Zeitschriftenartikel
109-111, Pt. A, S. 565 - 568 (2016)
Assessment of the W7-X high heat flux divertor with thermo-mechanical analysis. Fusion Engineering and Design