Publication | Closed Access
Preliminary engineering design of toroidal field magnet system for superconducting tokamak HT-7U
10
Citations
2
References
2000
Year
MagnetismMagnetic Confinement Fusion PhysicsEngineeringPreliminary Engineering DesignControlled Nuclear FusionFusion PowerMagnetohydrodynamicsPlasma PhysicsMagnetic ConfinementFusion Reactor MaterialTokamak Fusion ReactorMagnetic Confinement FusionCoil WindingStability Analysis
HT-7U is a large fusion experimental device. It will be built at the Institute of Plasma Physics of Chinese Academy of Sciences. The mission of HT-7U is to develop the scientific basis for a continuously operating tokamak fusion reactor. This paper describes only the toroidal field (TF) superconducting magnet system of HT-7U. In this paper, design criteria of conductor and stability analysis, coil winding and support structure design of magnet system, mechanical calculation, stress analysis and heat load evaluation are given.
| Year | Citations | |
|---|---|---|
Page 1
Page 1