Publications of G. Ehrke
All genres
Journal Article (26)
21.
Journal Article
57, 102020 (2017)
Major results from the first plasma campaign of the Wendelstein 7-X stellarator. Nuclear Fusion 22.
Journal Article
109-111, Pt. A, pp. 773 - 776 (2016)
Prototyping phase of the high heat flux scraper element of Wendelstein 7-X. Fusion Engineering and Design 23.
Journal Article
42 (3), pp. 542 - 532 (2014)
Status of High Heat Flux Components at W7-X. IEEE Transactions on Plasma Science 24.
Journal Article
40 (3, Part 1), pp. 769 - 776 (2012)
The Superconducting Magnet System of the Stellarator Wendelstein 7-X. IEEE Transcations on Plasma Science 25.
Journal Article
20 (3), pp. 447 - 450 (2010)
Design, Tests, and Repair Procedures for the Electrical Insulation of the Superconducting W7-X Magnets. IEEE Transactions on Applied Superconductivity 26.
Journal Article
84 (2-6), pp. 729 - 732 (2009)
Transition of W7-X non-planar coils from manufacturing to assembly. Fusion Engineering and Design Conference Paper (2)
27.
Conference Paper
Wendelstein 7-X High Heat Flux Components. In: 2013 IEEE 25th Symposium on Fusion Engineering (SOFE), 8 pp.. 25th Symposium on Fusion Engineering (SOFE 2013), San Francisco, CA, June 10, 2013 - June 14, 2013. IEEE, Piscataway, NJ (2013)
28.
Conference Paper
The superconducting magnet system of the stellarator Wendelstein 7-X. In: 24th IEEE/NPSS Symposium on Fusion Engineering (SOFE), S03D-3 (6pp). 24th Symposium on Fusion Engineering (SOFE), Chicago, IL, June 26, 2011 - June 30, 2011. IEEE, New York, NY (2011)
Talk (7)
29.
Talk
Tungsten based target element development for Wendelstein 7-X. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (submitted)
30.
Talk
Divertor concept development for the W7-X stellarator experiment. 4th IAEA Technical Meeting on Divertor Concepts, Vienna (submitted)
31.
Talk
Use of Carbon Fibre-reinforced Carbon in Wendelstein 7-X. TMS 2021 Virtual Annual Meeting & Exhibition, Virtual (2021)
32.
Talk
Use of Carbon Fibre-reinforced Carbon in Wendelstein 7-X. TMS2021 - Composite Materials for Nuclear Applications, Virtual (submitted)
33.
Talk
Material erosion and deposition on the divertor and vessel walls of W7-X. 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-17), Eindhoven (submitted)
34.
Talk
Refined Multiphysics Analysis of W7-X Cryopumps. 27th IEEE Symposium on Fusion Engineering (SOFE 2017), Shanghai (submitted)
35.
Talk
The superconducting magnet system of the stellarator Wendelstein 7-X. 38th IEEE International Conference on Plasma Science (ICOPS) and 24th Symposium on Fusion Engineering (SOFE), Chicago, IL (2011)
Poster (14)
36.
Poster
First Operation and Validation of Simulations for the Divertor Cyro-vacuum Pumps in W7-X. 29th IAEA Fusion Energy Conference (FEC 2023), London (submitted)
37.
Poster
Conceptual design of the next generation of W7-X divertor W-target elements. 32nd Symposium on Fusion Technology (SOFT 2022), Dubrovnik, Virtual (submitted)
38.
Poster
Completion of the production of the W7-X divertor target modules. 31st Symposium on Fusion Technology (SOFT 2020), Virtual Edition (submitted)
39.
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 (submitted)
40.
Poster
Progress in the production of the W7-X divertor target modules. 30th Symposium on Fusion Technology (SOFT 2018), Giardini Naxos (submitted)