DocumentCode :
2723583
Title :
ITER compact design
Author :
Torossian, A. ; Libeyre, P. ; Bertrand, B. ; Portafaix, C.
Author_Institution :
CEA, Centre d´´Etudes Nucleaires de Cadarache, France
Volume :
2
fYear :
1993
fDate :
11-15 Oct 1993
Firstpage :
671
Abstract :
This work has been performed on the basis of the version of ITER proposed by P.H. Rebut: central solenoid used as a bucking post for the TF coils, layer winding instead of pancake winding. The purpose of this work is not to propose a different project but to investigate solutions which minimize the radial thickness of the TF coils. To reach this goal, two concepts have been analysed and integrated in the whole design of the project: (A) Displacement of the steel needed to resist the hoop force of the TF coils from its usual place, located between the TF and CS windings, to the central area left free by the central solenoid. This new central post is designed in such a way that it also provides a precompression system which prevents sliding between the TF coils and the central solenoid. (B) Use of round conductor which is the less expensive to manufacture and to wind. Hexagonal arrangement of round conductors which homogenizes the stress distribution in the winding pack. These suggestions added to a few others should allow to increase the available flux by 20%
Keywords :
Tokamak devices; fusion reactor design; fusion reactors; CS windings; ITER compact design; TF coils; bucking post; central solenoid; hexagonal arrangement; hoop force; layer winding; pancake winding; precompression system; radial thickness; round conductor; steel; stress distribution; winding pack; Assembly; Coils; Conductors; Machining; Manufacturing; Nose; Resists; Solenoids; Steel; Stress;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
Conference_Location :
Hyannis, MA
Print_ISBN :
0-7803-1412-3
Type :
conf
DOI :
10.1109/FUSION.1993.518418
Filename :
518418
Link To Document :
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