HT-7U

E433907

HT-7U is a Chinese next-generation superconducting tokamak designed for advanced magnetic confinement fusion research and long-pulse plasma experiments.

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Predicate Object
instanceOf magnetic confinement fusion device
superconducting tokamak
alsoKnownAs EAST
Experimental Advanced Superconducting Tokamak
contributesTo DEMO reactor design studies
ITER physics basis
coolingSystem cryogenic cooling for superconducting magnets
country China
designedBy Institute of Plasma Physics, Chinese Academy of Sciences
designedFor high-confinement mode operation
non-inductive current drive
designedForPulseLength >1000 s
firstPlasmaYear 2006
fundingCountry China
hasDivertor true
heatingMethod electron cyclotron resonance heating
ion cyclotron resonance heating
lower hybrid current drive
neutral beam injection
locatedAt Institute of Plasma Physics, Chinese Academy of Sciences
locatedIn Hefei, Anhui, China
linked to: Hefei
majorRadius 1.85 m
minorRadius 0.45 m
operator Institute of Plasma Physics, Chinese Academy of Sciences
partOfProgram Chinese national fusion research program
plasmaCurrentDesign 1 MA
plasmaFacingComponents graphite tiles
tungsten divertor elements
plasmaShape divertor tokamak
plasmaVolume ~30 m^3
predecessor HT-7
projectType next-generation tokamak
purpose advanced magnetic confinement fusion research
long-pulse plasma experiments
steady-state tokamak operation research
researchFocus H-mode confinement
advanced plasma heating and current drive
plasma-wall interaction
steady-state operation scenarios
scientificGoal demonstrate long-pulse, high-parameter plasma operation
support development of future fusion power plants
technology superconducting poloidal field coils
superconducting toroidal field coils
toroidalFieldOnAxisDesign 3.5 T
vacuumVesselMaterial stainless steel

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