Publikationen von A. Peacock
Alle Typen
Zeitschriftenartikel (49)
21.
Zeitschriftenartikel
88 (9-10), S. 1660 - 1663 (2013)
Lessons learned from the design and fabrication of the baffles and heat shields of Wendelstein 7-X. Fusion Engineering and Design 22.
Zeitschriftenartikel
88 (9-10), S. 1727 - 1730 (2013)
Thermo-mechanical analysis of Wendelstein 7-X plasma facing components. Fusion Engineering and Design 23.
Zeitschriftenartikel
88 (9-10), S. 1764 - 1767 (2013)
Hydraulic analysis of the Wendelstein 7-X cooling loops. Fusion Engineering and Design 24.
Zeitschriftenartikel
88 (9-10), S. 1686 - 1689 (2013)
Challenges in the Realization of the In-Vessel-Components of Wendelstein 7-X. Fusion Engineering and Design 25.
Zeitschriftenartikel
87 (7-8), S. 1453 - 1456 (2012)
Design improvement of the target elements of Wendelstein 7-X divertor. Fusion Engineering and Design 26.
Zeitschriftenartikel
86 (6-8), S. 572 - 575 (2011)
Design and technological solutions for the plasma facing components of WENDELSTEIN 7-X. Fusion Engineering and Design 27.
Zeitschriftenartikel
86 (9-11), S. 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 28.
Zeitschriftenartikel
86 (9-11), S. 1669 - 1672 (2011)
Design analysis and manufacturing of the cooling lines of the in vessel components of WENDELSTEIN 7-X. Fusion Engineering and Design 29.
Zeitschriftenartikel
86 (9-11), S. 1706 - 1709 (2011)
The procurement and testing of the stainless steel in-vessel panels of the Wendelstein 7-X Stellarator. Fusion Engineering and Design 30.
Zeitschriftenartikel
86 (6-8), S. 728 - 731 (2011)
W7-X neutral-beam-injection: Selection of the NBI source positions for experiment start-up. Fusion Engineering and Design, Special Issue 31.
Zeitschriftenartikel
86 (9-11), S. 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 32.
Zeitschriftenartikel
86 (9-11), S. 1630 - 1633 (2011)
Thermo-mechanical analysis of the Wendelstein 7-X divertor. Fusion Engineering and Design 33.
Zeitschriftenartikel
84 (7-11), S. 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 34.
Zeitschriftenartikel
84 (7-11), S. 1525 - 1530 (2009)
Mechanical and thermo-physical characterization of three-directional carbon fiber composites for W7-X and ITER. Fusion Engineering and Design 35.
Zeitschriftenartikel
84 (2-6), S. 305 - 308 (2009)
The in-vessel components of the experiment Wendelstein 7-X. Fusion Engineering and Design 36.
Zeitschriftenartikel
10 (4), S. 727 - 731 (2008)
The long term development of fusion materials in the EU: achievements and open issues. Journal of Optoelectronics and Advanced Materials 37.
Zeitschriftenartikel
83 (7-9), S. 1015 - 1019 (2008)
Status of the EU R&D programme on the blanket-shield modules for ITER. Fusion Engineering and Design 38.
Zeitschriftenartikel
290-293, S. 491 - 495 (2001)
Hydrogen Isotope Depth Profiling in Carbon Samples from the Erosion Dominated Inner Vessel Walls of JET. Journal of Nuclear Materials 39.
Zeitschriftenartikel
266-269, S. 14 - 29 (1999)
In-vessel tritium retention and removal in ITER. Journal of Nuclear Materials 40.
Zeitschriftenartikel
T81, S. 13 - 18 (1999)
Transport and redeposition of eroded material in JET. Physica Scripta