Tokamak КТМ
Parameters
Major plasma radius |
0,9 м |
Minor plasma radius |
0,45 |
Аspect ratio A, m |
2 |
Plasma elongation К95 |
1,7 |
Toroidal magnetic field on axis Вто |
1 |
Maximum plasma current, MA |
0,75 |
Current plateau duration |
2–5 |
Auxiliary heating power Paux, MW |
8 |
Heat load on divertor plates, MW/m2 |
2–20 |
What is Tokamak?
A tokamak is a Toroidal Chamber with Magnetic Coils designed for research in the field of controlled thermonuclear fusion.
Design Features of KTM
- A megaampere-class facility with an aspect ratio A = 2 for testing materials and technologies under both normal and emergency operating conditions (including plasma disruption modes).
- Establishment of a steady-state plasma discharge regime with temperatures exceeding 10 million K using additional RF heating with power up to 8 MW.
- Creation of steady-state edge plasma flows into the divertor region with power loads up to 20 MW/m2, comparable to or exceeding the divertor and first-wall heat loads in ITER.
- Development of systems enabling rapid replacement of divertor plate materials, adjustment of plasma flux reception conditions and intensities, fast pumping, and other operational capabilities.
- Adjustable plasma flux power through:
- variation of the distance from the separatrix X-point to the divertor plates;
- changing the inclination angle of the divertor plates relative to the tokamak axis;
- sweeping the separatrix X-point using an additional poloidal field coil.