DocumentCode :
3200549
Title :
Manufacturing and assembly status of main components of the Wendelstein 7-X Cryostat
Author :
Koppe, Torsten ; Cardella, A. ; Reich, J. ; Missal, B. ; Hein, B. ; Krause, R. ; Jenzsch, H. ; Hermann, D. ; Schrader, M. ; Di Bartolo, G. ; Leher, F. ; Binni, A. ; Segl, J. ; Camin, R. ; Giordano, L. ; Langone, S. ; Ridzewski, J. ; Corniani, Giorgio
Author_Institution :
Max-Planck-IPP, EURATOM Assoc., Greifswald, Germany
fYear :
2009
fDate :
1-5 June 2009
Firstpage :
1
Lastpage :
4
Abstract :
Wendelstein 7-X (W7-X) will be the world´s largest superconducting helical advanced stellarator. This stellarator fusion experiment is at present in assembly at the Max-Planck-Institut fur Plasmaphysik (IPP). W7-X is deemed to be a desirable alternative for a future power plant like DEMO. The main advance of the static plasma is caused by the three-dimensional shape of some of the main mechanical components inside the Cryostat. The toroidal plasma with a ring diameter of 11 m and an average plasma diameter of 1.1 m is contained within the Plasma Vessel. Its form is dictated by the shape of the plasma. Its geometry is formed around the three-dimensional shape of the plasma. The form of the plasma is controlled by the coil system configuration. In order to control the plasma form it is necessary that all the 20 planar and 50 non planar coils be positioned within a tolerance of 1.5 mm. To meet this requirement a complex coil support structure was created, consisting of the Central Support Ring and the different inter coil supports. The coils and the support structure are enclosed within the Outer Vessel with its domes and openings. The space between the Outer and the Plasma Vessel is called Cryostat because the vacuum inside provides thermal insulation of the magnet system. The entire magnetic system is then cooled down to 4 K. Due to different thermal movements the Plasma Vessel and the Central Support Ring have to be supported separately. The Central Support Ring is held by 10 Cryo Legs. The Plasma Vessel supporting system is divided into two separate systems, allowing horizontal and vertical adjustments to centre the Plasma Vessel during thermal expansion. This paper aims to give an overview of the main components in the Cryostat like the Plasma Vessel, the Outer Vessel, the ports and the different support systems. It describes the current manufacturing and assembly status and the associated problems of these components, using pictures and text.
Keywords :
cryostats; fusion reactor ignition; fusion reactor materials; plasma radiofrequency heating; plasma toroidal confinement; stellarators; thermal expansion; DEMO; ECRH; ICRH; Max-Planck-Institut fur Plasmaphysik; NBI; Wendelstein 7-X cryostat components; central support ring; coil system configuration; future power plant; in-vessel components; in-vessel maintenance; magnet system; mechanical components; nonplanar coils; planar coils; plasma vessel; size 1.1 m; size 1.5 mm; size 11 m; superconducting helical advanced stellarator; thermal expansion; thermal insulation; toroidal plasma; Assembly; Coils; Geometry; Magnetic separation; Manufacturing; Plasma materials processing; Power generation; Shape; Superconducting magnets; Toroidal magnetic fields; Central Support Ring; Coil Support Structure; Cryo Legs; Cryostat; Magnetic System; Outer Vessel; Plasma Vessel; Stellerator; Wendelstein 7-X;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on
Conference_Location :
San Diego, CA
Print_ISBN :
978-1-4244-2635-5
Electronic_ISBN :
978-1-4244-2636-2
Type :
conf
DOI :
10.1109/FUSION.2009.5226448
Filename :
5226448
Link To Document :
بازگشت