Publications of A. Peacock
All genres
Journal Article (49)
2013
Journal Article
88 (9-10), pp. 1660 - 1663 (2013)
Lessons learned from the design and fabrication of the baffles and heat shields of Wendelstein 7-X. Fusion Engineering and Design
Journal Article
88 (9-10), pp. 1727 - 1730 (2013)
Thermo-mechanical analysis of Wendelstein 7-X plasma facing components. Fusion Engineering and Design
Journal Article
88 (9-10), pp. 1764 - 1767 (2013)
Hydraulic analysis of the Wendelstein 7-X cooling loops. Fusion Engineering and Design
Journal Article
88 (9-10), pp. 1686 - 1689 (2013)
Challenges in the Realization of the In-Vessel-Components of Wendelstein 7-X. Fusion Engineering and Design 2012
Journal Article
87 (7-8), pp. 1453 - 1456 (2012)
Design improvement of the target elements of Wendelstein 7-X divertor. Fusion Engineering and Design 2011
Journal Article
86 (6-8), pp. 572 - 575 (2011)
Design and technological solutions for the plasma facing components of WENDELSTEIN 7-X. Fusion Engineering and Design
Journal Article
86 (9-11), pp. 1685 - 1688 (2011)
Performance and statistical quality assessment of CFC tile bonding on the pre-series elements of the Wendelstein 7-X divertor. Fusion Engineering and Design
Journal Article
86 (9-11), pp. 1669 - 1672 (2011)
Design analysis and manufacturing of the cooling lines of the in vessel components of WENDELSTEIN 7-X. Fusion Engineering and Design
Journal Article
86 (9-11), pp. 1706 - 1709 (2011)
The procurement and testing of the stainless steel in-vessel panels of the Wendelstein 7-X Stellarator. Fusion Engineering and Design
Journal Article
86 (6-8), pp. 728 - 731 (2011)
W7-X neutral-beam-injection: Selection of the NBI source positions for experiment start-up. Fusion Engineering and Design, Special Issue
Journal Article
86 (9-11), pp. 1732 - 1735 (2011)
Development of a thermo-hydraulic bypass leakage test method for the Wendelstein 7-X target element cooling structure. Fusion Engineering and Design
Journal Article
86 (9-11), pp. 1630 - 1633 (2011)
Thermo-mechanical analysis of the Wendelstein 7-X divertor. Fusion Engineering and Design 2009
Journal Article
84 (7-11), pp. 1475 - 1478 (2009)
Progress in the design and development of a test divertor (TDU) for the start of W7-X operation. Fusion Engineering and Design
Journal Article
84 (7-11), pp. 1525 - 1530 (2009)
Mechanical and thermo-physical characterization of three-directional carbon fiber composites for W7-X and ITER. Fusion Engineering and Design
Journal Article
84 (2-6), pp. 305 - 308 (2009)
The in-vessel components of the experiment Wendelstein 7-X. Fusion Engineering and Design 2008
Journal Article
10 (4), pp. 727 - 731 (2008)
The long term development of fusion materials in the EU: achievements and open issues. Journal of Optoelectronics and Advanced Materials
Journal Article
83 (7-9), pp. 1015 - 1019 (2008)
Status of the EU R&D programme on the blanket-shield modules for ITER. Fusion Engineering and Design 2001
Journal Article
290-293, pp. 491 - 495 (2001)
Hydrogen Isotope Depth Profiling in Carbon Samples from the Erosion Dominated Inner Vessel Walls of JET. Journal of Nuclear Materials 1999
Journal Article
266-269, pp. 14 - 29 (1999)
In-vessel tritium retention and removal in ITER. Journal of Nuclear Materials
Journal Article
T81, pp. 13 - 18 (1999)
Transport and redeposition of eroded material in JET. Physica Scripta