Wendelstein 7-X
E538653
Wendelstein 7-X is a large experimental stellarator-type nuclear fusion device in Germany designed to study and optimize magnetically confined plasma for future fusion power plants.
Observed surface forms (1)
| Surface form | Occurrences |
|---|---|
| Wendelstein 7-X collaboration | 1 |
Statements (53)
| Predicate | Object |
|---|---|
| instanceOf |
magnetic confinement fusion device
ⓘ
nuclear fusion experiment ⓘ stellarator ⓘ |
| abbreviation | W7-X NERFINISHED ⓘ |
| coilType | superconducting ⓘ |
| constructionStart | 2005 ⓘ |
| coolant | liquid helium ⓘ |
| coolingMethod | cryogenic cooling ⓘ |
| country | Germany NERFINISHED ⓘ |
| designedFor |
high-confinement plasma studies
ⓘ
steady-state plasma operation ⓘ testing reactor-relevant plasma scenarios ⓘ |
| designedToTest | island divertor concept ⓘ |
| deviceType | toroidal magnetic confinement device ⓘ |
| firstHydrogenPlasmaDate | 2016-02-03 ⓘ |
| firstPlasmaDate | 2015-12-10 ⓘ |
| fuelType |
deuterium
ⓘ
hydrogen ⓘ |
| fundedBy |
German Federal Government
NERFINISHED
ⓘ
state of Mecklenburg-Vorpommern NERFINISHED ⓘ |
| fusionConcept | stellarator NERFINISHED ⓘ |
| hasComponent |
cryostat
ⓘ
divertor ⓘ microwave heating system ⓘ modular superconducting coil system ⓘ vacuum vessel ⓘ |
| locatedAt | Max Planck Institute for Plasma Physics NERFINISHED ⓘ |
| locatedIn | Greifswald NERFINISHED ⓘ |
| magneticConfiguration |
heliotron-like
ⓘ
optimized stellarator ⓘ |
| magneticFieldStrength | up to 3 tesla ⓘ |
| mainObjective |
demonstrate steady-state operation capability
ⓘ
optimize stellarator configuration for future fusion power plants ⓘ study magnetically confined plasma ⓘ |
| majorRadius | 5.5 m ⓘ |
| minorRadius | 0.53 m ⓘ |
| namedAfter | Wendelstein series of stellarators NERFINISHED ⓘ |
| numberOfFieldPeriods | 5 ⓘ |
| numberOfNonPlanarCoils | 50 ⓘ |
| numberOfPlanarCoils | 20 ⓘ |
| operatedBy | Max Planck Institute for Plasma Physics NERFINISHED ⓘ |
| partOf | Max Planck Society NERFINISHED ⓘ |
| plannedHeatingPower | up to 20 MW ⓘ |
| plasmaHeatingMethod |
ECRH
NERFINISHED
ⓘ
electron cyclotron resonance heating ⓘ |
| plasmaVolume | about 30 m³ ⓘ |
| predecessor | Wendelstein 7-AS NERFINISHED ⓘ |
| researchField |
fusion energy
ⓘ
plasma physics ⓘ |
| researchGoal |
assess suitability of stellarators for power plant operation
ⓘ
demonstrate good plasma confinement in optimized stellarator geometry ⓘ |
| safetyCharacteristic | no self-sustaining fusion reactions planned ⓘ |
| status | operational experimental device ⓘ |
Referenced by (2)
Full triples — surface form annotated when it differs from this entity's canonical label.
this entity surface form:
Wendelstein 7-X collaboration