Publications of J. Boscary
All genres
Journal Article (81)
2024
Journal Article
201, 114268 (2024)
Galvanic process for Cu-infiltration of W fibre-reinforced heat sinks. Fusion Engineering and Design 2023
Journal Article
192, 113629 (2023)
Conceptual design of the next generation of W7-X divertor W-target elements. Fusion Engineering and Design 2022
Journal Article
175, 112986 (2022)
Thermal loading test of a Wendelstein 7-X pumping gap panel. Fusion Engineering and Design
Journal Article
62, 042022 (2022)
Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X. Nuclear Fusion 2021
Journal Article
166, 112293 (2021)
Completion of the production of the W7-X divertor target modules. Fusion Engineering and Design 2020
Journal Article
161, 111882 (2020)
Thermal and mechanical analyses of W7-X plasma facing components for operation phase 2. Fusion Engineering and Design 2019
Journal Article
146, Pt. B, pp. 1975 - 1978 (2019)
Progress in the production of the W7-X divertor target modules. Fusion Engineering and Design
Journal Article
146, Pt. B, pp. 2757 - 2760 (2019)
Design and manufacturing of the Wendelstein 7-X cryo-vacuum pump. Fusion Engineering and Design
Journal Article
146, Pt. A, pp. 1166 - 1170 (2019)
Repair processes of Wendelstein 7-X target modules. Fusion Engineering and Design
Journal Article
59, 112004 (2019)
Overview of first Wendelstein 7-X high-performance operation. Nuclear Fusion
Journal Article
59, 066041 (2019)
Measurement and modeling of magnetic configurations to mimic overload scenarios in the W7-X stellarator. Nuclear Fusion 2018
Journal Article
46 (5), pp. 1398 - 1401 (2018)
Design and Test of Wendelstein 7-X Water-Cooled Divertor Scraper. IEEE Transactions on Plasma Science
Journal Article
46 (5), pp. 1387 - 1392 (2018)
Modeling and Preparation for Experimental Testing of Heat Fluxes on W7-X Divertor Scraper Elements. IEEE Transactions on Plasma Science
Journal Article
46 (5), pp. 1576 - 1579 (2018)
Thermal and Mechanical Analysis of the Wendelstein 7-X Cryo-Vacuum Pump Plug-In. IEEE Transactions on Plasma Science 2017
Journal Article
124, pp. 348 - 351 (2017)
Summary of the production of the divertor target elements of Wendelstein 7-X. Fusion Engineering and Design
Journal Article
121, pp. 211 - 217 (2017)
Thermal-hydraulics modeling for prototype testing of the W7-X high heat flux scraper element. Fusion Engineering and Design
Journal Article
T170, 014045 (2017)
Examinations for leak tightness of actively cooled components in ITER and fusion devices. Physica Scripta
Journal Article
T170, 019601 (2017)
Erratum: Examinations for leak tightness of actively cooled components in ITER and fusion devices (2017 Phys. Scr. 2017 014045). Physica Scripta
Journal Article
124, pp. 483 - 486 (2017)
Local copper coating of the connectors of the divertor target elements of Wendelstein 7-X. Fusion Engineering and Design
Journal Article
124, pp. 292 - 296 (2017)
Structural analysis of the W7-X cryopump during the superconducting coil fast discharge event. Fusion Engineering and Design