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Zeitschriftenartikel (76)
61.
Zeitschriftenartikel
T128, S. 218 - 221 (2007)
Power load limits of the WENDELSTEIN 7-X target elements - comparison of experimental results and design values for power loads up to the critical heat flux. Physica Scripta 62.
Zeitschriftenartikel
367-370, S. 1444 - 1448 (2007)
High Heat Flux Facility GLADIS - Operational Characteristics and Results of W7-X Pre-Series Target Tests. Journal of Nuclear Materials 63.
Zeitschriftenartikel
82, S. 1713 - 1719 (2007)
High heat flux tests of the WENDELSTEIN 7-X pre-series target elements - Experimental evaluation of the thermo-mechanical behaviour. Fusion Engineering and Design 64.
Zeitschriftenartikel
T128, S. 182 - 188 (2007)
Qualification of high heat flux components: application to target elements of W7-X divertor. Physica Scripta 65.
Zeitschriftenartikel
82, S. 1747 - 1755 (2007)
Infrared thermography inspection methods applied to the target elements of W7-X divertor. Fusion Engineering and Design 66.
Zeitschriftenartikel
T128, S. 204 - 208 (2007)
CFC/Cu bond damage in actively cooled plasma facing components. Physica Scripta 67.
Zeitschriftenartikel
75-79, S. 463 - 468 (2005)
Manufacturing of the Wendelstein 7-X divertor and wall protection. Fusion Engineering and Design 68.
Zeitschriftenartikel
75-79, S. 451 - 455 (2005)
Applied technologies and inspections for the W7-X pre-series target elements. Fusion Engineering and Design 69.
Zeitschriftenartikel
46, S. 318 - 326 (2004)
Physical Aspects and Design of the Wendelstein 7-X Divertor. Fusion Science and Technology 70.
Zeitschriftenartikel
43, S. 831 - 834 (2003)
Water-cooled target modules for steady-state operation of the W7-X divertor. Nuclear Fusion 71.
Zeitschriftenartikel
66-68, S. 447 - 452 (2003)
Final design of W7-X divertor plasma facing components – tests and thermo-mechanical analysis of baffle prototypes. Fusion Engineering and Design 72.
Zeitschriftenartikel
313-316, S. 1298 - 1303 (2003)
Neutral particle modelling and particle exhaust in the Wendelstein 7-X stellarator. Journal of Nuclear Materials 73.
Zeitschriftenartikel
44 (6), S. 1005 - 1019 (2002)
Divertor concept for the W7-X stellarator and mode of operation. Plasma Physics and Controlled Fusion 74.
Zeitschriftenartikel
56-57, S. 279 - 283 (2001)
Optimisation of target plates for the W7-X divertor at stationary operation. Fusion Engineering and Design 75.
Zeitschriftenartikel
40, S. 1083 - 1093 (2000)
The Capabilities of Steady State Operation at the Stellarator W7-X with Emphasis on Divertor Design. Nuclear Fusion 76.
Zeitschriftenartikel
29 (4), S. 417 - 448 (1996)
Toward long-pulse, high-performance discharges in Tore Supra: Experimental knowledge and technological developments for heat exhaust. Fusion Technology Konferenzbeitrag (13)
77.
Konferenzbeitrag
Measurement and Modeling of Magnetic Configurations to Mimic Overload Scenarios in the W7-X Stellarator. In: 27th IAEA Fusion Energy Conference, EX/P8-19. 27th IAEA Fusion Energy Conference (FEC 2018), Gandhinagar (Ahmedabad), 22. Oktober 2018 - 27. Oktober 2018. International Atomic Energy Agency, Vienna (2019)
78.
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)
79.
Konferenzbeitrag
Development activities for the target elements of the Wendelstein 7-X divertor. In: 2013 IEEE 25th Symposium on Fusion Engineering (SOFE), 6 pp.. 25th Symposium on Fusion Engineering (SOFE 2013), San Francisco, CA, 10. Juni 2013 - 14. Juni 2013. IEEE, Piscataway, NJ (2013)
80.
Konferenzbeitrag
Physics and Engineering Design of the Divertor Scraper Element for the W7-X Stellarator. In: 2013 IEEE 25th Symposium on Fusion Engineering (SOFE), 5 pp.. 25th Symposium on Fusion Engineering (SOFE 2013), San Francisco, CA, 10. Juni 2013 - 14. Juni 2013. IEEE, Piscataway, NJ (2013)