Publikationen von A. T. Peacock
Alle Typen
Zeitschriftenartikel (49)
1999
Zeitschriftenartikel
266-269, S. 604 - 610 (1999)
Wall erosion and material transport to the Mark I carbon divertor of JET. Journal of Nuclear Materials 1997
Zeitschriftenartikel
: High performance Joint European Torus (JET) plasmas for deuterium-tritium operation with the MkII divertor. Physics of Plasmas 4 (5), S. 1725 - 1735 (1997)
Zeitschriftenartikel
241-243, S. 469 - 475 (1997)
Erosion at the vessel walls of JET. Journal of Nuclear Materials 1995
Zeitschriftenartikel
: JET results with the new pumped divertor and implications for ITER. Plasma Physics and Controlled Fusion 37 (Suppl. 11A), S. A3 - A17 (1995)
1994
Zeitschriftenartikel
: First Results with the modified JET - The JET Team. Plasma Physics and Controlled Fusion 36 (12B Suppl. S), S. B39 - B53 (1994)
Zeitschriftenartikel
212, S. 1245 - 1249 (1994)
Modification of the carbon and beryllium walls in JET by erosion, redeposition and deuterium trapping after the 1991 discharge period. Journal of Nuclear Materials
Zeitschriftenartikel
: Overview of high performance H-modes in JET. Plasma Physics and Controlled Fusion 36 (7 Suppl. A), S. A23 - A38 (1994)
1992
Zeitschriftenartikel
196-198, S. 729 - 734 (1992)
Deuterium trapping and impurity collection on a 1990 JET Be belt limiter. Journal of Nuclear Materials
Zeitschriftenartikel
: The JET preliminary tritium experiment. Plasma Physics and Controlled Fusion 34 (13), S. 1749 - 1758 (1992)
Konferenzbeitrag (8)
2013
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)
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)
Konferenzbeitrag
Heat Flux and Design Calculations for the W7-X Divertor Scraper Element. In: Proceedings of the 24th IAEA Fusion Energy Conference, FTP/P1-02. 24th IAEA Fusion Energy Conference 2012, San Diego, CA, 08. Oktober 2012 - 13. Oktober 2012. International Atomic Energy Agency, Vienna (2013)
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)
2011
Konferenzbeitrag
: 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, 26. Juni 2011 - 30. Juni 2011. IEEE, New York, NY (2011)
2003
Konferenzbeitrag
: The design of a new JET divertor for high triangularity and high current scenarios. 22. Symposium on Fusion Technology (SOFT-22), Helsinki (FI), 09. September 2002 - 13. September 2002. Fusion Engineering and Design 66-68, S. 407 - 411 (2003)
2002
Konferenzbeitrag
61-62, S. 61 - 70 (2002)
Status of Fabrication Development for Plasma Facing Components in the EU. Proceedings of the 6. International Symposium on Fusion Nuclear Technology, San Diego, CA(US), 07. April 2002 - 12. April 2002. Proceedings of the 6. International Symposium on Fusion Nuclear Technology 1991
Konferenzbeitrag
Bachmann, P.; Robinson, D. C.). 18th EPS Conference on Controlled Fusion and Plasma Physics, Berlin (DE), 03. Juni 1991 - 07. Juni 1991. European Physical Society, Geneva (1991)
Deuterium Depth Profiles and Impurities on the Be Coated Carbon Belt Limiter in JET. In: 18th European Physical Society Conference on Controlled Fusion and Plasma Physics, S. 153 - 156 (Hg. Vortrag (14)
2014
Vortrag
Multiphysics Analysis of the Wendelstein 7-X Actively Cooled Divertor Scraper Element. 21st Topical Meeting on the Technology of Fusion Energy (TOFE) , Anaheim, US (eingereicht)
Vortrag
Analysis of the Wendelstein 7-X Test Divertor Unit Scraper Element with Radiation Shields. 21st Topical Meeting on the Technology of Fusion Energy (TOFE), Anaheim, CA (eingereicht)
2013
Vortrag
: Wendelstein 7-X: Status of Project Construction and Commissioning Planning. 11th International Symposium on Fusion Nuclear Technology (ISFNT-11), Barcelona (2013)