
Publikationen von M. Czerwinski
Alle Typen
Zeitschriftenartikel (8)
1.
Zeitschriftenartikel
175, 112986 (2022)
Thermal loading test of a Wendelstein 7-X pumping gap panel. Fusion Engineering and Design 2.
Zeitschriftenartikel
59, 112004 (2019)
Overview of first Wendelstein 7-X high-performance operation. Nuclear Fusion 3.
Zeitschriftenartikel
136, Pt. A, S. 292 - 297 (2018)
Overview of fatigue life assessment of baffles in Wendelstein 7-X. Fusion Engineering and Design 4.
Zeitschriftenartikel
57, 102020 (2017)
Major results from the first plasma campaign of the Wendelstein 7-X stellarator. Nuclear Fusion 5.
Zeitschriftenartikel
42 (3), S. 542 - 532 (2014)
Status of High Heat Flux Components at W7-X. IEEE Transactions on Plasma Science 6.
Zeitschriftenartikel
82, S. 1467 - 1472 (2007)
Design aspects of the joints for the bus bar system of the Wendelstein 7-X stellarator. Fusion Engineering and Design 7.
Zeitschriftenartikel
82, S. 1526 - 1531 (2007)
Test results from the full size prototype test of W7-X joint. Fusion Engineering and Design 8.
Zeitschriftenartikel
43, S. 831 - 834 (2003)
Water-cooled target modules for steady-state operation of the W7-X divertor. Nuclear Fusion Konferenzbeitrag (3)
9.
Konferenzbeitrag
2, S. 1006 - 1017 (Hg. Ascione, L.; Berardi, V.; Feo, L.; Fraternali, F.; Tralli, M.). 23rd Conference "The Italian Association of Theoretical and Applied Mechanics" (AIMETA 2017), Salerno, 04. September 2017 - 07. September 2017. The Italian Association of Theoretical and Applied Mechanics (2017)
Crack modelling in baffle modules of nuclear fusion experiment "Wendelstein 7-X". In: AIMETA 2017 – Proceedings of the XXIII Conference of the Italian Association of Theoretical and Applied Mechanics, Bd. 10.
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)
11.
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)
Vortrag (5)
12.
Vortrag
Engineering of the W7-X Divertor, Target Design, Vessel Integration of Components. W7-X Divertor Symposium, Greifswald (2020)
13.
Vortrag
Divertor Development for W7-X. W7-X Divertor Symposium, Greifswald (2020)
14.
Vortrag
LCF assessment for baffle modules of nuclear fusion experiment "Wendelstein 7-X". 23rd Conference "The Italian Association of Theoretical and Applied Mechanics" (AIMETA 2017), Salerno (eingereicht)
15.
Vortrag
The results from the full size prototype test of W7-X joint. 24th Symposium on Fusion Technology (SOFT 2006), Warsaw (2006)
16.
Vortrag
Physics, Technologies and Status of the Wendelstein 7-X Device. 20th IAEA Fusion Energy Conference, Vilamoura (2004)
Poster (3)
17.
Poster
Fatigue Life Assessment of Baffles in Wendelstein 7-X. 13th International Symposium on Fusion Nuclear Technology (ISFNT-13), Kyoto (eingereicht)
18.
Poster
Conceptual design of the W7-X in vessel port protection for steady state operation. 28th Symposium on Fusion Technology (SOFT 2014)
, San Sebastian (2014)
19.
Poster
The First Experience in the Assembly of the W7-X Stellarator. 24th Symposium on Fusion Technology (SOFT 2006), Warsaw (2006)