DocumentCode
2152681
Title
Alternative structural concepts for the Fusion Ignition Research Experiment (FIRE)
Author
Titus, Peter H.
Author_Institution
Plasma Sci. & Fusion Center, MIT, Cambridge, MA, USA
fYear
2002
fDate
2002
Firstpage
200
Lastpage
204
Abstract
The baseline toroidal field coil system of the FIRE tokamak utilizes inertially cooled, copper alloy Bitter plate type magnets which are LN2 cooled between shots. The TF configuration is wedged and uses C17510 high strength, high conductivity beryllium copper alloy which was developed for BPX in the inner leg, where the stress is highest. In FY 01, a slightly larger design was adopted (R=2.14 m. compared to the previous 2.0 m.)which affords better physics performance with lower TF field, and thus lower TF stresses. Bucked and wedged (B&W) TF designs have also been considered. The B&W design results in lower coil stresses in the inner leg that may be used to increase field or design margin, or alternatively could allow the use of high conductivity OFHC copper which would allow longer pulse lengths. B&W designs require good fit-up, and effects of fit-up uncertainties, friction factor variations, and methods of evaluating primary load paths are presented. The effects of the size change and possible changes in structural concept are summarized.
Keywords
beryllium alloys; copper alloys; electromagnets; fusion reactor design; fusion reactor materials; fusion reactor theory; 2.14 m; Be-Cu; Bitter plate type magnets; C17510; Cu alloy; FIRE; Fusion Ignition Research Experiment; N2; bucked and wedged design; coil stress; friction factor; high conductivity OFHC copper; Coils; Conductivity; Copper alloys; Fires; Ignition; Leg; Magnets; Physics; Stress; Tokamaks;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 2002. 19th Symposium on
Print_ISBN
0-7803-7073-2
Type
conf
DOI
10.1109/FUSION.2002.1027676
Filename
1027676
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