DocumentCode :
1948060
Title :
Building block support structure for HELIAS Stellarator reactors
Author :
Schauer, F. ; Egorov, K. ; Bykov, V. ; Dudek, A.
Author_Institution :
Max-Planck-Inst. fur Plasmaphysik (IPP), Teilinstitut Greifswald, Greifswald, Germany
fYear :
2011
fDate :
26-30 June 2011
Firstpage :
1
Lastpage :
6
Abstract :
An engineering design study is being performed on an enhanced version of a “Helical Advanced Stellarator” (HELIAS) reactor which is based on a fourfold up-scaled W7-X. The coil sizes, their maximal conductor field of 12.3 T, and their operation conditions are similar to those of the ITER TF coils which means that many of the ITER magnet technologies can be applied. The mechanical structure of the first design iteration step has been sub-divided into manageable building block panels for easier manufacture and assembly. The screwed panels between the coils are dismountable which opens up the possibility to separate the torus for maintenance as an alternative to the usually considered exchange of divertor and blanket components through the ports.
Keywords :
Tokamak devices; fusion reactor blankets; fusion reactor divertors; fusion reactor operation; plasma toroidal confinement; stellarators; HELIAS stellarator reactors; ITER TF coils; ITER magnet technologies; blanket component; block support structure; building block panels; coil sizes; divertor component; fourfold up-scaled W7-X; helical advanced stellarator reactor; maximal conductor field; mechanical structure; operation conditions; Maintenance engineering; Welding; Fusion reactor; HELIAS; finite element analysis; mechanical structure; stellarator; torus separation;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
Conference_Location :
Chicago, IL
ISSN :
1078-8891
Print_ISBN :
978-1-4577-0669-1
Electronic_ISBN :
1078-8891
Type :
conf
DOI :
10.1109/SOFE.2011.6052243
Filename :
6052243
Link To Document :
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