HT-7U
E433907
HT-7U is a Chinese next-generation superconducting tokamak designed for advanced magnetic confinement fusion research and long-pulse plasma experiments.
All labels observed (1)
| Label | Occurrences |
|---|---|
| HT-7U canonical | 1 |
Statements (45)
| Predicate | Object |
|---|---|
| instanceOf |
magnetic confinement fusion device
ⓘ
superconducting tokamak ⓘ |
| alsoKnownAs |
EAST
NERFINISHED
ⓘ
Experimental Advanced Superconducting Tokamak NERFINISHED ⓘ |
| 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 NERFINISHED ⓘ |
| designedFor |
high-confinement mode operation
ⓘ
non-inductive current drive ⓘ |
| designedForPulseLength | >1000 s ⓘ |
| firstPlasmaYear | 2006 ⓘ |
| fundingCountry | China NERFINISHED ⓘ |
| 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 NERFINISHED ⓘ |
| locatedIn | Hefei, Anhui, China NERFINISHED ⓘ |
| majorRadius | 1.85 m ⓘ |
| minorRadius | 0.45 m ⓘ |
| operator | Institute of Plasma Physics, Chinese Academy of Sciences NERFINISHED ⓘ |
| 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 NERFINISHED ⓘ |
| 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 ⓘ |
Referenced by (1)
Full triples — surface form annotated when it differs from this entity's canonical label.