Publikationen von R. Tivey
Alle Typen
Konferenzbeitrag (28)
21.
Konferenzbeitrag
Part A ; s. 39-40, S. 377 - 384 (1998)
Design of the ITER EDA Plasma Facing Components. ISFNT-4, Tokyo (JP), 06. April 1997 - 11. April 1997. Proceedings of the 4. International Symposium on Fusion Nuclear Technology 22.
Konferenzbeitrag
Vol. 1, S. 331 - 336 (1998)
Status of the Engineering Design of the ITER Divertor. SOFE '97, San Diego, CA(US), 06. Oktober 1997 - 10. Oktober 1997. 17. IEEE/NPSS Symposium Fusion Engineering 23.
Konferenzbeitrag
Vol. 1, S. 203 - 206 (1998)
The Attachment System of the ITER Divertor Plasma Facing Components. 20. SOFT, Marseille (FR), 07. November 1998 - 11. November 1998. Fusion Technology 1998 24.
Konferenzbeitrag
Vol. 2, S. 1693 - 1696 (1998)
ITER Heat Removal System. System & Process Control Design. 20. SOFT, Marseille (FR), 07. November 1998 - 11. November 1998. Fusion Technology 1998 25.
Konferenzbeitrag
Vol. 1, S. 75 (1998)
Critical Design Issues of New Semitransparent Liner for ITER Divertor Cassette. 20. SOFT, Marseille (FR), 07. November 1998 - 11. November 1998. Fusion Technology 1998 26.
Konferenzbeitrag
Part A ; s. 258-263, S. 74 - 84 (1998)
Design and Material Selection for ITER First Wall/Blanket, Divertor and Vacuum Vessel. 8. International Conference on Fusion Reactor Materials, Sendai (JP), 26. Oktober 1997 - 31. Oktober 1997. Fusion Reactor Materials 27.
Konferenzbeitrag
Part A ; s. 39-40, S. 173 - 187 (1998)
Divertor Development for ITER. ISFNT-4, Tokyo (JP), 06. April 1997 - 11. April 1997. Proceedings of the 4. International Symposium on Fusion Nuclear Technology 28.
Konferenzbeitrag
Vol. 2, S. 965 - 968 (1998)
Progress in the Design of the ITER Divertor Maintenance System. SOFE '97, San Diego, CA(US), 06. Oktober 1997 - 10. Oktober 1997. 17. IEEE/NPSS Symposium Fusion Engineering 29.
Konferenzbeitrag
Part A ; s. 39-40, S. 323 - 331 (1998)
High Heat Flux Thermal-Hydraulic Analysis of ITER Divertor and Blanket Systems. ISFNT-4, Tokyo (JP), 06. April 1997 - 11. April 1997. Proceedings of the 4. International Symposium on Fusion Nuclear Technology 30.
Konferenzbeitrag
Vol. 2, S. 1641 - 1644 (1997)
ITER Divertor PFC's Attachment and Replacement. 19. SOFT, Amsterdam Lisbon (PT). Fusion Technology 31.
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 32.
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)
33.
Konferenzbeitrag
Vol. 2, S. 1633 - 1636 (1997)
Design of the ITER Divertor Remote Handling System. 19. SOFT, Amsterdam Lisbon (PT). Fusion Technology 34.
Konferenzbeitrag
Vol. 1, S. 279 - 282 (1997)
Engineering Design of the ITER Divertor. 19. SOFT, Amsterdam Lisbon (PT). Fusion Technology 35.
Konferenzbeitrag
Vol. 1, S. 144 - 149 (1996)
The ITER Divertor. SOFE '95, Champaign, IL(US). 16th IEEE/NPSS Symposium Fusion Engineering 36.
Konferenzbeitrag
A Plasma Protection Tile Concept Based on a Contact Provided by Thermally Induced Expansion. In: Proc. of the 18th Symposium on Fusion Technology, Vol. 1, S. 219 - 222. Proc. of the 18th Symposium on Fusion Technology, Vol. 1, Amsterdam Karlsruhe (DE). North-Holland Publ. (1995)
37.
Konferenzbeitrag
Design of ITER Divertor Cassettes. In: Proc. of the 18th Symposium on Fusion Technology, Vol. 1, S. 339 - 342. Proc. of the 18th Symposium on Fusion Technology, Vol. 1, Amsterdam Karlsruhe (DE). North-Holland Publ. (1995)
Vortrag (2)
38.
Vortrag
Cyclic Heat Load Testing of Improved CFC/Cu Bonding for the W7-X Divertor Targets. 13th International Conference on Fusion Reactor Materials (ICFRM-13), Nice (2007)
39.
Vortrag
Testing of improved CFC/Cu Bondings for the W7-X Divertor Targets. 13th International Conference on Fusion Reactor Materials (ICFRM-13), Nice (2007)
Poster (3)
40.
Poster
Development of a thermo-hydraulic bypass leakage test method for the Wendelstein 7-X target element cooling structure. 26th Symposium on Fusion Technology (SOFT 2010), Porto (2010)