Publikationen von A. T. Peacock
Alle Typen
Zeitschriftenartikel (49)
41.
Zeitschriftenartikel
266-269, S. 604 - 610 (1999)
Wall erosion and material transport to the Mark I carbon divertor of JET. Journal of Nuclear Materials 42.
Zeitschriftenartikel
4 (5), S. 1725 - 1735 (1997)
High performance Joint European Torus (JET) plasmas for deuterium-tritium operation with the MkII divertor. Physics of Plasmas 43.
Zeitschriftenartikel
241-243, S. 469 - 475 (1997)
Erosion at the vessel walls of JET. Journal of Nuclear Materials 44.
Zeitschriftenartikel
37 (Suppl. 11A), S. A3 - A17 (1995)
JET results with the new pumped divertor and implications for ITER. Plasma Physics and Controlled Fusion 45.
Zeitschriftenartikel
36 (12B Suppl. S), S. B39 - B53 (1994)
First Results with the modified JET - The JET Team. Plasma Physics and Controlled Fusion 46.
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 47.
Zeitschriftenartikel
36 (7 Suppl. A), S. A23 - A38 (1994)
Overview of high performance H-modes in JET. Plasma Physics and Controlled Fusion 48.
Zeitschriftenartikel
196-198, S. 729 - 734 (1992)
Deuterium trapping and impurity collection on a 1990 JET Be belt limiter. Journal of Nuclear Materials 49.
Zeitschriftenartikel
34 (13), S. 1749 - 1758 (1992)
The JET preliminary tritium experiment. Plasma Physics and Controlled Fusion Konferenzbeitrag (8)
50.
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)
51.
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)
52.
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)
53.
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)
54.
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)
55.
Konferenzbeitrag
66-68, S. 407 - 411 (2003)
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 56.
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 57.
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)
58.
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)
59.
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)
60.
Vortrag
Wendelstein 7-X: Status of Project Construction and Commissioning Planning. 11th International Symposium on Fusion Nuclear Technology (ISFNT-11), Barcelona (2013)