Publikationen von J. Tretter
Alle Typen
Zeitschriftenartikel (24)
21.
Zeitschriftenartikel
86 (6-8), S. 689 - 693 (2011)
Alternative conceptual design of a magnet support structure for plasma fusion devices of stellarator type. Fusion Engineering and Design 22.
Zeitschriftenartikel
84 (7-11), S. 1475 - 1478 (2009)
Progress in the design and development of a test divertor (TDU) for the start of W7-X operation. Fusion Engineering and Design 23.
Zeitschriftenartikel
75-79, S. 565 - 569 (2005)
Manufacture of the vacuum vessels and the ports of Wendelstein 7-X. Fusion Engineering and Design 24.
Zeitschriftenartikel
75-79, S. 565 - 569 (2004)
Manufacture of the Plasma vessels and the ports for Wendelstein 7-X. Fusion Engineering and Design Konferenzbeitrag (8)
25.
Konferenzbeitrag
CFD analysis of actively cooled divertor target element for stellarator W7-X. In: Proceedings of the 30th International Conference on Nuclear Energy for New Europe (NENE), S. 812.1 - 812.8 (Hg. Cizelj, L.; Tekavcic, M.). 30th International Conference Nuclear Energy for New Europe (NENE 2021), Bled, 06. September 2021 - 09. September 2021. Nuclear Society of Ljubljana, Ljubljana (2021)
26.
Konferenzbeitrag
Thermal-fluid modeling of single- and two-phase flows in the W7-X high heat flux divertor scraper element. In: 2015 IEEE 26th Symposium on Fusion Engineering (SOFE). 26th IEEE Symposium on Fusion Engineering (SOFE 2015), Austin, TX, 31. Mai 2015 - 04. Juni 2015. IEEE, New York, NY (2015)
27.
Konferenzbeitrag
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, 10. Juni 2013 - 14. Juni 2013. IEEE, Piscataway, NJ (2013)
28.
Konferenzbeitrag
A proposed scraper element to protect the end of the W7-X divertor target elements. In: 24th IEEE/NPSS Symposium on Fusion Engineering (SOFE), SP2-41 (5pp). 24th Symposium on Fusion Engineering (SOFE), Chicago, IL, 26. Juni 2011 - 30. Juni 2011. IEEE, New York, NY (2011)
29.
Konferenzbeitrag
Design and test of the support elements of the W7-X magnet system. In: Proceedings 21st IEEE/NPSS Symposium on Fusion Engineering, 04_10. 21st IEEE/NPSS Symposium on Fusion Engineering (SOFE 05), Knoxville, TN, 26. September 2005 - 29. September 2005. IEEE, Piscataway, NJ (2006)
30.
Konferenzbeitrag
Critical Design Issues of Wendelstein 7-X. In: 15th International Stellarator Workshop and IAEA Technical Meeting on Innovative Concepts and Theory of Stellarator, Or-08. 15th International Stellarator Workshop, Madrid, 03. Oktober 2005 - 07. Oktober 2005. International Atomic Energy Agency, Vienna (2006)
31.
Konferenzbeitrag
Physics, Technologies and Status of the Wendelstein 7-X Device. In: 20th IAEA Fusion Energy Conference Proceedings, FT/3-5. 20th IAEA Fusion Energy Conference, Vilamoura, 01. November 2004 - 06. November 2004. International Atomic Energy Agency, Vienna (2005)
32.
Konferenzbeitrag
Demonstration Cryostat Sector for Wendelstein 7-X. In: Proc. of the 18th Symposium on Fusion Technology, Vol. 2, S. 941 - 944 (Hg. Herschbach, K.; Maurer, W.; Vetter, J. E.). Proc. of the 18th Symposium on Fusion Technology, Vol. 2, Amsterdam Karlsruhe (DE). North-Holland Publ. (1995)
Vortrag (20)
33.
Vortrag
Status of PLS system integration. 42nd Technical Coordination Meeting (TCM-42) of the Satellite Tokamak Programme, Padova (eingereicht)
34.
Vortrag
Tungsten based target element development for Wendelstein 7-X. 19th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC-19), Bonn (eingereicht)
35.
Vortrag
Divertor concept development for the W7-X stellarator experiment. 4th IAEA Technical Meeting on Divertor Concepts, Vienna (eingereicht)
36.
Vortrag
Density control strategy for AUG, JT-60SA and EU-DEMO. 26th TC Topical Group Meeting (eingereicht)
37.
Vortrag
CFD analysis of actively cooled divertor target element for stellarator W7-X. 30th International Conference Nuclear Energy for New Europe (NENE 2021), Bled (eingereicht)
38.
Vortrag
Pellet actuator development step by step: from AUG to JT60-SA and EU-DEMO. QST Large Tokamak Seminar, Naka (eingereicht)
39.
Vortrag
Design and test of W7-X water-cooled Divertor Scraper. 27th IEEE Symposium on Fusion Engineering (SOFE 2017), Shanghai (eingereicht)
40.
Vortrag
Two-Phase Thermal-Fluid Analysis of the W7-X High Heat Flux Divertor Scraper Element. 26th IEEE Symposium on Fusion Engineering (SOFE 2015), Austin, TX (2015)