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Design, Analysis and R&D of the EAST In-Vessel Components
25
Citations
3
References
2008
Year
EngineeringFlow ControlPlasma PhysicsOceanographyStructural OptimizationMagnetic Confinement FusionNaval ArchitectureIn-vessel CoilsEast In-vessel ComponentsDivertor PhysicsPlasma TheoryPlasma SimulationControlled Nuclear FusionPlasma ConfinementApplied Plasma PhysicMagnetic ConfinementShip ResistancePropulsionHeat TransferPassive PlatesStrength Of ShipAerospace Engineering
In-vessel components are important parts of the EAST superconducting tokamak. They include the plasma facing components, passive plates, cryo-pumps, in-vessel coils, etc. The structural design, analysis and related R&D have been completed. The divertor is designed in an up-down symmetric configuration to accommodate both double null and single null plasma operation. Passive plates are used for plasma movement control. In-vessel coils are used for the active control of plasma vertical movements. Each cryo-pump can provide an approximately 45 m3/s pumping rate at a pressure of 10−1 Pa for particle exhaust. Analysis shows that, when a plasma current of 1 MA disrupts in 3 ms, the EM loads caused by the eddy current and the halo current in a vertical displacement event (VDE) will not generate an unacceptable stress on the divertor structure. The bolted divertor thermal structure with an active cooling system can sustain a load of 2 MW/m2 up to a 60 s operation if the plasma facing surface temperature is limited to 1500 °C. Thermal testing and structural optimization testing were conducted to demonstrate the analysis results.
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