Publications of J. Tretter
All genres
Journal Article (24)
21.
Journal Article
86 (6-8), pp. 689 - 693 (2011)
Alternative conceptual design of a magnet support structure for plasma fusion devices of stellarator type. Fusion Engineering and Design 22.
Journal Article
84 (7-11), pp. 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.
Journal Article
75-79, pp. 565 - 569 (2005)
Manufacture of the vacuum vessels and the ports of Wendelstein 7-X. Fusion Engineering and Design 24.
Journal Article
75-79, pp. 565 - 569 (2004)
Manufacture of the Plasma vessels and the ports for Wendelstein 7-X. Fusion Engineering and Design Conference Paper (8)
25.
Conference Paper
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), pp. 812.1 - 812.8 (Eds. Cizelj, L.; Tekavcic, M.). 30th International Conference Nuclear Energy for New Europe (NENE 2021), Bled, September 06, 2021 - September 09, 2021. Nuclear Society of Ljubljana, Ljubljana (2021)
26.
Conference Paper
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, May 31, 2015 - June 04, 2015. IEEE, New York, NY (2015)
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
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, June 26, 2011 - June 30, 2011. IEEE, New York, NY (2011)
29.
Conference Paper
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, September 26, 2005 - September 29, 2005. IEEE, Piscataway, NJ (2006)
30.
Conference Paper
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, October 03, 2005 - October 07, 2005. International Atomic Energy Agency, Vienna (2006)
31.
Conference Paper
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, November 01, 2004 - November 06, 2004. International Atomic Energy Agency, Vienna (2005)
32.
Conference Paper
Demonstration Cryostat Sector for Wendelstein 7-X. In: Proc. of the 18th Symposium on Fusion Technology, Vol. 2, pp. 941 - 944 (Eds. Herschbach, K.; Maurer, W.; Vetter, J. E.). Proc. of the 18th Symposium on Fusion Technology, Vol. 2, Amsterdam Karlsruhe (DE). North-Holland Publ. (1995)
Talk (20)
33.
Talk
Status of PLS system integration. 42nd Technical Coordination Meeting (TCM-42) of the Satellite Tokamak Programme, Padova (submitted)
34.
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)
35.
Talk
Divertor concept development for the W7-X stellarator experiment. 4th IAEA Technical Meeting on Divertor Concepts, Vienna (submitted)
36.
Talk
Density control strategy for AUG, JT-60SA and EU-DEMO. 26th TC Topical Group Meeting (submitted)
37.
Talk
CFD analysis of actively cooled divertor target element for stellarator W7-X. 30th International Conference Nuclear Energy for New Europe (NENE 2021), Bled (submitted)
38.
Talk
Pellet actuator development step by step: from AUG to JT60-SA and EU-DEMO. QST Large Tokamak Seminar, Naka (submitted)
39.
Talk
Design and test of W7-X water-cooled Divertor Scraper. 27th IEEE Symposium on Fusion Engineering (SOFE 2017), Shanghai (submitted)
40.
Talk
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)