Alternative structural concepts for the Fusion Ignition Research Experiment (FIRE)
Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231) - Trang 200-204
Tóm tắt
The baseline toroidal field coil system of the FIRE tokamak utilizes inertially cooled, copper alloy Bitter plate type magnets which are LN/sub 2/ 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.
Từ khóa
#Ignition #Fires #Stress #Coils #Copper alloys #Conductivity #Leg #Tokamaks #Magnets #PhysicsTài liệu tham khảo
yamamoto, 2001, Effect of electrode shape on fusion reaction rate in a cylindrical electrostatic confinement device, Fusion Technol, 39, 552, 10.13182/FST01-A172
miley, 1991, Inertial-Electrostatic Confinement: An Approach to Burning Advanced Fuels, Fusion Technol, 19, 840, 10.13182/FST91-3
yamamoto, 2001, Effect of electrode shape on Performance Characteristics of a Cylindrical Inertial Electrostatic Confinement Fusion Device, Fusion Technol, 39, 1188, 10.13182/FST01-A172
iwamoto, 2001, Preliminary Results of Cylindrical Electrostatic Confinement Experiment, Fusion Technol, 39, 557, 10.13182/FST01-A11963294
10.1016/0168-583X(95)00503-X
iwamoto, 2001, Study for discharge characteristics of a Cylindrical Inertial Electrostatic Confinement Fusion Device
gu, 1994, A Portable Cylindrical Electrostatic Fusion Device for Neutronic Tomography, Fusion Technol, 26, 929, 10.13182/FST94-A40273
10.1109/FUSION.1997.687733
hirsch, 1967, Inertial-Electrostatic Confinement of lonized Fusion Gasses, J Appl Phys, 38, 10.1063/1.1709162
