A5053966173- Magnetic confinement fusion research
- Fusion materials and technologies
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Particle accelerators and beam dynamics
Institute for Plasma Research
2021-2023
Controlling and mitigating plasma disruptions are a matter of serious concern for tokamak operation since they can cause damage to the machine. Dedicated experiments on disruption mitigation have been carried out in ADITYA (R = 75 cm, 25 cm), an Ohmically heated circular limiter tokamak. A rapid growth magneto hydrodynamic (MHD) modes is found be major Stimulated induced by hydrogen gas puffing successfully mitigated through stabilization these MHD applying biased-electrode placed inside...
In the ADITYA tokamak, plasma discharge is initiated through filament pre-ionization assisted breakdown, using conventional inductively driven electric field. Following breakdown of neutral gas, sustained by a successful burnthrough phase. The nature and phase studied varying parameters influencing it, such as toroidal field, operating pressure, lithium wall conditioning. initiation failures in are identified, optimized conditions derived. value Lloyd parameter Eϕ×BT/Bz for found to be range...