i. ADITYA-U: ADITYA-U is India’s medium-sized conventional air-core tokamak (major radius 0.75 m, minor radius 0.25 m), developed as the upgraded successor to the ADITYA tokamak, the country’s first indigenously developed magnetic confinement fusion device. The research work is aimed to support the development of operational scenarios, plasma-control techniques, and fusion technologies relevant to ITER and future fusion energy systems
ii. SST-1: SST-1 (Steady State Superconducting Tokamak-1) is India's first superconducting tokamak and was developed to advance magnetic confinement fusion research. It is designed for long-duration plasma operation, employing superconducting toroidal and poloidal field magnets. This tokamak features an array of advanced subsystems for plasma heating, including Electron Cyclotron Resonance Heating (ECRH) and Lower Hybrid Current Drive (LHCD), as well as various advanced diagnostics. The device is used to study plasma confinement, transport and stability, as well as plasma-wall interactions and steady-state operation. It also serves as a platform for developing technologies relevant to ITER and future fusion power reactors.
iii. ST: The Spherical Tokamak (ST) is a compact, low-aspect-ratio variant of the conventional tokamak. It is known for its ability to operate at a high plasma pressure relative to the magnetic field, which is a crucial advantage for future fusion reactors. This facility's primary objective is to conduct fundamental physics research into spherical tokamak equilibria, non-inductive plasma start-up and current sustainment, high-beta plasma operation and wall conditioning techniques.