Publikationen von G. Janeschitz
Alle Typen
Konferenzbeitrag (160)
101.
Konferenzbeitrag
Vol. 2, S. 1641 - 1644 (1997)
ITER Divertor PFC's Attachment and Replacement. 19. SOFT, Amsterdam Lisbon (PT). Fusion Technology 102.
Konferenzbeitrag
Vol. 2, S. 1689 - 1692 (1997)
Tokamak Component Handling, Maintenance and Associated Service Building. 19. SOFT, Amsterdam Lisbon (PT). Fusion Technology 103.
Konferenzbeitrag
Vol. 1, S. 347 - 350 (1997)
Materials Aspects of ITER In-Vessel Components. 19. SOFT, Amsterdam Lisbon (PT). Fusion Technology 104.
Konferenzbeitrag
s. 241-243, S. 260 - 267 (1997)
The Influence of Key Operation Parameters and Material Properties on the Quantification of Tritium Inventory and Permeation in the Plasma Facing Components of ITER. Proceedings of the 12. International Conference on Plasma-Surface Interactions in Controlled Fusion Devices, Saint-Raphael (FR). Journal of Nuclear Materials 105.
Konferenzbeitrag
21A, 3, S. 989 - 992 (1997)
MHD Ballooning Stability of ITER Equilibria. 24th EPS Conference on Controlled Fusion and Plasma Physics, Berchtesgaden (DE), 09. Juni 1997 - 13. Juni 1997. ECA 106.
Konferenzbeitrag
Vol. 2, S. 755 - 767 (1997)
ITER Divertor, and Pumping and Fuelling System Designs. 16. International Conference on Fusion Energy, Montreal (CA), 07. Oktober 1996 - 11. Oktober 1996. Fusion Energy 1996 107.
Konferenzbeitrag
Vol. 2, S. 987 - 993 (1997)
Analysis of ITER Divertor Performance and ITER Tokamak Edge Parameter Database. 16. International Conference on Fusion Energy, Montreal (CA), 07. Oktober 1996 - 11. Oktober 1996. Fusion Energy 1996 108.
Konferenzbeitrag
Vol. 2, S. 1173 - 1176 (1997)
The Design of the ITER Primary Pumping System. 19. SOFT, Amsterdam Lisbon (PT). Fusion Technology 109.
Konferenzbeitrag
Status of development of remote maintenance of ITER divertor cassettes. In: Fusion Energy 1996. Proceedings of the 16th International Conference on Fusion Energy, S. 905 - 916. 16th International Conference on Fusion Energy, Montreal, 07. Oktober 1996 - 11. Oktober 1996. International Atomic Energy Agency (IAEA), Vienna (1997)
110.
Konferenzbeitrag
Vol. 2, S. 1633 - 1636 (1997)
Design of the ITER Divertor Remote Handling System. 19. SOFT, Amsterdam Lisbon (PT). Fusion Technology 111.
Konferenzbeitrag
Vol. 2, S. 1125 - 1128 (1997)
Status of ITER and Wall Conditioning System Design. 19. SOFT, Amsterdam Lisbon (PT). Fusion Technology 112.
Konferenzbeitrag
s. 241-243, S. 255 - 259 (1997)
Erosion Lifetime of ITER Divertor Plates. Proceedings of the 12. International Conference on Plasma-Surface Interactions in Controlled Fusion Devices, Saint-Raphael (FR). Journal of Nuclear Materials 113.
Konferenzbeitrag
s. 241-243, S. 1 - 26 (1997)
Plasma-Wall Interactions in ITER. Proceedings of the 12. International Conference on Plasma-Surface Interactions in Controlled Fusion Devices, Saint-Raphael (FR). Journal of Nuclear Materials 114.
Konferenzbeitrag
21A, 3, S. 1041 - 1044 (1997)
The Alfven Drift-Wave Instability and the Scaling of the Edge Temperature at the L-H Transition. 24th EPS Conference on Controlled Fusion and Plasma Physics, Berchtesgaden (DE), 09. Juni 1997 - 13. Juni 1997. ECA 115.
Konferenzbeitrag
s. 241-243, S. 299 - 304 (1997)
Modelling of Transition from Attached to Detached State and Self-Consistent Calculations of He Levels in ITER. Proceedings of the 12. International Conference on Plasma-Surface Interactions in Controlled Fusion Devices, Saint-Raphael (FR). Journal of Nuclear Materials 116.
Konferenzbeitrag
Vol. 1, S. 279 - 282 (1997)
Engineering Design of the ITER Divertor. 19. SOFT, Amsterdam Lisbon (PT). Fusion Technology 117.
Konferenzbeitrag
Vol. 1, S. 849 - 852 (1997)
Engineering Aspects of ITER Plasma Diagnostic Systems. 19. SOFT, Amsterdam Lisbon (PT). Fusion Technology 118.
Konferenzbeitrag
Langmuir Probes and Optical Diagnostics for the ITER Divertor. Proc. of the International Workshop on Diagnostics for ITER, New York,NY Varenna (IT). Diagnostics for Experimental Thermonuclear Fusion Reactors, S. 591 - 594 (1996)
119.
Konferenzbeitrag
Vol. 1, S. 144 - 149 (1996)
The ITER Divertor. SOFE '95, Champaign, IL(US). 16th IEEE/NPSS Symposium Fusion Engineering 120.
Konferenzbeitrag
Vol. 1, S. 430 - 434 (1996)
Analysis of Heat Transfer and Erosion Effects on ITER Divertor Plasma Facing Components Induced by Slow High-Power Transients. SOFE '95, Champaign, IL(US). 16th IEEE/NPSS Symposium Fusion Engineering