Experimental Advanced Superconducting Tokamak
E97804
The Experimental Advanced Superconducting Tokamak (EAST) is a Chinese magnetic confinement fusion research reactor designed to study and advance tokamak-based fusion energy technologies.
All labels observed (2)
| Label | Occurrences |
|---|---|
| Experimental Advanced Superconducting Tokamak canonical | 2 |
| ITER project | 1 |
Statements (48)
| Predicate | Object |
|---|---|
| instanceOf |
fusion research reactor
ⓘ
magnetic confinement fusion device ⓘ tokamak ⓘ |
| abbreviation | EAST ⓘ |
| alsoKnownAs | HT-7U ⓘ |
| constructionStart | early 2000s ⓘ |
| contributesTo | R&D for ITER-relevant steady-state operation ⓘ |
| country | China ⓘ |
| designedBy |
Hefei Institutes of Physical Science, Chinese Academy of Sciences
ⓘ
surface form:
Institute of Plasma Physics, Chinese Academy of Sciences
|
| designedFor | long-pulse plasma discharges ⓘ |
| firstPlasma | 2006 ⓘ |
| fundingSource |
People's Republic of China government
ⓘ
surface form:
Chinese government
|
| goal |
advance technologies for future fusion power plants
ⓘ
demonstrate steady-state high-performance plasma operation ⓘ |
| hasComponent |
cryogenic system
ⓘ
diagnostic systems ⓘ divertor system ⓘ plasma heating and current drive systems ⓘ superconducting poloidal field coils ⓘ superconducting toroidal field coils ⓘ vacuum vessel ⓘ |
| heatingMethod |
electron cyclotron resonance heating
ⓘ
ion cyclotron resonance heating ⓘ lower hybrid current drive ⓘ neutral beam injection ⓘ |
| location |
Anhui
ⓘ
Hefei ⓘ |
| magneticCoilsType | superconducting ⓘ |
| majorRadius | approximately 1.85 meters ⓘ |
| minorRadius | approximately 0.45 meters ⓘ |
| operator |
Hefei Institutes of Physical Science, Chinese Academy of Sciences
ⓘ
surface form:
Institute of Plasma Physics, Chinese Academy of Sciences
|
| plasmaCurrent | up to about 1 megaampere ⓘ |
| plasmaShape | diverted, elongated plasma ⓘ |
| purpose |
magnetic confinement fusion research
ⓘ
study of tokamak-based fusion energy technologies ⓘ |
| recordType | long-duration high-temperature plasma discharges ⓘ |
| relatedTo | ITER ⓘ |
| researchFocus |
advanced plasma control
ⓘ
high-confinement modes ⓘ plasma heating and current drive ⓘ plasma-wall interactions ⓘ steady-state operation of tokamaks ⓘ |
| sector | nuclear fusion research ⓘ |
| supportsExperiment |
H-mode confinement studies
ⓘ
divertor and edge plasma physics ⓘ plasma stability and disruption studies ⓘ |
| technology | superconducting tokamak ⓘ |
| toroidalFieldOnAxis | about 3.5 tesla ⓘ |
Referenced by (3)
Full triples — surface form annotated when it differs from this entity's canonical label.
this entity surface form:
ITER project
Hefei Institutes of Physical Science, Chinese Academy of Sciences
→
operates
→
Experimental Advanced Superconducting Tokamak
ⓘ