Statements (56)
| Predicate | Object |
|---|---|
| gptkbp:instanceOf |
fusion device
|
| gptkbp:challenge |
material limitations
energy confinement time neutron flux plasma instabilities tritium breeding |
| gptkbp:component |
gptkb:plasma
blanket divertor magnetic coils vacuum vessel |
| gptkbp:confinementMethod |
magnetometer
|
| gptkbp:confinementTime |
measured in seconds
|
| gptkbp:countryOfOrigin |
gptkb:Soviet_Union
|
| gptkbp:developedBy |
1950s
|
| gptkbp:etymology |
Russian acronym for 'toroidal chamber with magnetic coils'
|
| gptkbp:fuelType |
deuterium
tritium |
| gptkbp:goal |
achieve controlled nuclear fusion
commercial fusion power |
| https://www.w3.org/2000/01/rdf-schema#label |
tokamaks
|
| gptkbp:inventedBy |
Soviet physicists
|
| gptkbp:limitation |
complexity
disruptions size and cost |
| gptkbp:magneticFieldStrength |
poloidal field
toroidal field |
| gptkbp:notableExample |
gptkb:COMPASS
gptkb:SPARC gptkb:Alcator_C-Mod gptkb:DIII-D gptkb:EAST gptkb:ITER gptkb:JET gptkb:JT-60 gptkb:KSTAR gptkb:T-15 gptkb:TFTR |
| gptkbp:operatingStatus |
experimental
|
| gptkbp:plasmaCurrent |
induced by transformer action
|
| gptkbp:plasmaTemperature |
tens of millions of degrees Celsius
|
| gptkbp:principle |
induced plasma current
magnetic field lines |
| gptkbp:relatedTo |
inertial confinement fusion
spheromaks stellarators |
| gptkbp:researchArea |
energy research
nuclear fusion plasma physics |
| gptkbp:shape |
toroidal
|
| gptkbp:trainHeating |
neutral beam injection
ohmic heating radiofrequency heating |
| gptkbp:usedFor |
magnetic confinement fusion
|
| gptkbp:bfsParent |
gptkb:Langmuir_probe
|
| gptkbp:bfsLayer |
4
|