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.
Aliases (1)
- 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 |
Institute of Plasma Physics, Chinese Academy of Sciences
→
|
| designedFor |
long-pulse plasma discharges
→
|
| firstPlasma |
2006
→
|
| fundingSource |
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 |
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)
| Subject (surface form when different) | Predicate |
|---|---|
|
Fusion Energy Sciences program
("ITER project")
→
|
collaboratesWith |
|
Hefei
→
|
hasResearchFacility |
|
Hefei Institutes of Physical Science, Chinese Academy of Sciences
→
|
operates |