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
4 (5), pp. 1725 - 1735 (1997)
High performance Joint European Torus (JET) plasmas for deuterium-tritium operation with the MkII divertor. Physics of Plasmas 43.
Journal Article
241-243, pp. 469 - 475 (1997)
Erosion at the vessel walls of JET. Journal of Nuclear Materials 44.
Journal Article
37 (Suppl. 11A), pp. A3 - A17 (1995)
JET results with the new pumped divertor and implications for ITER. Plasma Physics and Controlled Fusion 45.
Journal Article
36 (12B Suppl. S), pp. B39 - B53 (1994)
First Results with the modified JET - The JET Team. Plasma Physics and Controlled Fusion 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
36 (7 Suppl. A), pp. A23 - A38 (1994)
Overview of high performance H-modes in JET. Plasma Physics and Controlled Fusion 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
34 (13), pp. 1749 - 1758 (1992)
The JET preliminary tritium experiment. Plasma Physics and Controlled Fusion 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
66-68, pp. 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), September 09, 2002 - September 13, 2002. Fusion Engineering and Design 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)