Publications of A. T. Peacock
All genres
Journal Article (49)
41.
Journal Article
266-269, pp. 604 - 610 (1999)
Wall erosion and material transport to the Mark I carbon divertor of JET. Journal of Nuclear Materials 42.
Journal Article
: High performance Joint European Torus (JET) plasmas for deuterium-tritium operation with the MkII divertor. Physics of Plasmas 4 (5), pp. 1725 - 1735 (1997)
43.
Journal Article
241-243, pp. 469 - 475 (1997)
Erosion at the vessel walls of JET. Journal of Nuclear Materials 44.
Journal Article
: JET results with the new pumped divertor and implications for ITER. Plasma Physics and Controlled Fusion 37 (Suppl. 11A), pp. A3 - A17 (1995)
45.
Journal Article
: First Results with the modified JET - The JET Team. Plasma Physics and Controlled Fusion 36 (12B Suppl. S), pp. B39 - B53 (1994)
46.
Journal Article
212, pp. 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.
Journal Article
: Overview of high performance H-modes in JET. Plasma Physics and Controlled Fusion 36 (7 Suppl. A), pp. A23 - A38 (1994)
48.
Journal Article
196-198, pp. 729 - 734 (1992)
Deuterium trapping and impurity collection on a 1990 JET Be belt limiter. Journal of Nuclear Materials 49.
Journal Article
: The JET preliminary tritium experiment. Plasma Physics and Controlled Fusion 34 (13), pp. 1749 - 1758 (1992)
Conference Paper (8)
50.
Conference Paper
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, June 10, 2013 - June 14, 2013. IEEE, Piscataway, NJ (2013)
51.
Conference Paper
: 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, June 10, 2013 - June 14, 2013. IEEE, Piscataway, NJ (2013)
52.
Conference Paper
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, October 08, 2012 - October 13, 2012. International Atomic Energy Agency, Vienna (2013)
53.
Conference Paper
: 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, June 10, 2013 - June 14, 2013. IEEE, Piscataway, NJ (2013)
54.
Conference Paper
: 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, June 26, 2011 - June 30, 2011. IEEE, New York, NY (2011)
55.
Conference Paper
: The design of a new JET divertor for high triangularity and high current scenarios. 22. Symposium on Fusion Technology (SOFT-22), Helsinki (FI), September 09, 2002 - September 13, 2002. Fusion Engineering and Design 66-68, pp. 407 - 411 (2003)
56.
Conference Paper
61-62, pp. 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), April 07, 2002 - April 12, 2002. Proceedings of the 6. International Symposium on Fusion Nuclear Technology 57.
Conference Paper
Bachmann, P.; Robinson, D. C.). 18th EPS Conference on Controlled Fusion and Plasma Physics, Berlin (DE), June 03, 1991 - June 07, 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, pp. 153 - 156 (Eds. Talk (14)
58.
Talk
Multiphysics Analysis of the Wendelstein 7-X Actively Cooled Divertor Scraper Element. 21st Topical Meeting on the Technology of Fusion Energy (TOFE) , Anaheim, US (submitted)
59.
Talk
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 (submitted)
60.
Talk
: Wendelstein 7-X: Status of Project Construction and Commissioning Planning. 11th International Symposium on Fusion Nuclear Technology (ISFNT-11), Barcelona (2013)