DocumentCode
2062036
Title
Alignment of the TFTR bumper limiter
Author
Barnes, G.W. ; Owens, D.K. ; Loesser, G.D. ; Ulrickson, M.
Author_Institution
Plasma Phys. Lab., Princeton Univ., NJ, USA
fYear
1989
fDate
2-6 Oct 1989
Firstpage
937
Abstract
The TFTR (Tokamak Fusion Test Reactor) bumper limiter (BL) is an axisymmetric toroidal limiter mounted on the inner wall of the vacuum vessel. It subtends 120° poloidally and has a surface area of 22 m 2. The plasma-facing surface consists of 1000 kg of graphite tiles mounted on water-cooled Inconel backing plates. During the initial installation in the Spring of 1985, the limiter surface was aligned to the toroidal magnetic field by mechanical and magnetic measurements to an estimated accuracy of ±2 mm. The methods used to mechanically align the limiter are described, and evidence, based on machine operation with a plasma, that the limiter is reasonably well aligned with the toroidal field is presented. Future work addressing the alignment of the total limiter to the toroidal field using mechanical and magnetic measurements and the replacement of a subset of the carbon times with carbon-carbon composite material is also discussed
Keywords
Tokamak devices; fusion reactor materials; fusion reactor theory and design; 1000 kg; C; C-C composite; Ni-Cr; TFTR; Tokamak Fusion Test Reactor; axisymmetric toroidal limiter; bumper limiter; graphite tiles; plasma-facing surface; toroidal field; water-cooled Inconel backing plates; Composite materials; Inductors; Magnetic variables measurement; Plasma materials processing; Plasma measurements; Springs; Testing; Tiles; Tokamaks; Toroidal magnetic fields;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location
Knoxville, TN
Type
conf
DOI
10.1109/FUSION.1989.102371
Filename
102371
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