A5063119481- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Particle accelerators and beam dynamics
- Ionosphere and magnetosphere dynamics
- Laser-Plasma Interactions and Diagnostics
- Atomic and Subatomic Physics Research
- Power System Optimization and Stability
- Real-time simulation and control systems
- Injection Molding Process and Properties
- Nuclear Physics and Applications
- Advanced Data Storage Technologies
- Embedded Systems and FPGA Design
- Nuclear reactor physics and engineering
- High-Energy Particle Collisions Research
- Magnetic Properties and Applications
- Advanced Fiber Optic Sensors
- Mineral Processing and Grinding
- Geophysical Methods and Applications
- Crystallization and Solubility Studies
- Gyrotron and Vacuum Electronics Research
- Nuclear Materials and Properties
- Advanced Sensor and Control Systems
- Smart Grid Security and Resilience
Institute for Plasma Research
2016-2024
Royal Military Academy
2020
The first Indian tokamak, ADITYA, operated for over two decades with a circular poloidal limiter, has been upgraded to tokamak named ADITYA Upgrade (ADITYA-U) attain shaped-plasma operations an open divertor in single and double-null configurations. Experimental research using ADITYA-U made significant progress since the last FEC 2016. After installation of plasma facing component standard diagnostics ADITYA-U, Phase-I were initiated December 2016 graphite toroidal belt limiter. Ohmically...
Abstract Since the 2018 IAEA-FEC conference, in addition to expanding parameter horizons of ADITYA-U machine, emphasis has been given dedicated experiments on inductively driven particle injection (IPI) for disruption studies, runaway electron (RE) dynamics and mitigation, plasma rotation reversal, radiative-improved modes using Ne Ar injection, modulation magneto–hydrodynamic modes, edge turbulence periodic gas puffs electrode biasing (E-B). Plasma parameters close design circular plasmas...
Abstract A first-of-its-kind, inductively driven micro-particle (Pellet) accelerator and injector have been developed operated successfully in ADITYA-U circular plasma operations, which may ably address the critical need for a suitable disruption control mechanism ITER future tokamak. The device combines principles of electromagnetic induction, pulse power technology, impact, fracture dynamics. It is designed to operate variety environments, including atmospheric pressure ultra-high vacuum....
Abstract The generation and subsequent loss of runaway electrons (REs) during the operation sequence in a tokamak is potent threat to plasma-facing components interface actively cooled parts. Control mitigation REs are prime importance safe machine health fusion device. A supersonic molecular beam injection (SMBI) system has been installed ADITYA-U explore effects high Mach number on ways mitigate REs. In majority discharges which SMBI injected, burst hard x-rays observed accompanying pulse,...
The influence of background plasma poloidal rotation on the frequency m/n = 2/1 drift tearing mode (DTM) has been studied in ADITYA-U tokamak. velocity ion diamagnetic direction is increased or decreased by inducing an outward inward radial electric field, respectively, through a biased-electrode placed edge region plasma. preexisting mode, rotating electron direction, concomitantly with application bias depending its polarity. positive-bias increases ion-diamagnetic from pre-bias value,...
Abstract The ADITYA upgrade (ADITYA-U), a medium-sized <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:mo>(</mml:mo> <mml:msub> <mml:mi>R</mml:mi> <mml:mn>0</mml:mn> </mml:msub> </mml:mrow> <mml:mo>=</mml:mo> <mml:mn>75</mml:mn> <mml:mtext> cm</mml:mtext> <mml:mo>,</mml:mo> <mml:mstyle scriptlevel="0"/> <mml:mi>a</mml:mi> <mml:mn>25</mml:mn> <mml:mo>)</mml:mo> </mml:math> conventional tokamak facility in India, has been consistently producing...
This paper describes the characterisation of a negative feedback type automatic gain control (AGC) circuit that will be an integral part heterodyne radiometer system operating at frequency range 75–86 GHz SST-1 tokamak. The developed AGC is combination variable amplifier and log which provides both attenuation typically up to 15 dB 45 dB, respectively, fixed set point voltage it has been explored for first time in tokamak radiometry application. other important characteristics are exhibits...
Electromagnetic (EM) Diagnostics is one of the most important diagnostics tools to measure key parameters such as current, position, loop voltage and Magneto Hydro Dynamic MHD activities plasma in SST1 (Steady State Tokamak), designed for long pulse (1000 s) operation. A frontend electronic scheme conditioning dynamic (10mV 2V) range signals over entire time span that incorporates features remote parameter setting, self-test calibration, saturation detection, storing default values system...
Refiectometry measures the beat frequency between radiated electromagnetic waves with a reference signal. We derive relation phase change, path length and sweep rate estimate of Data acquisition parameters are calculated based on sampling required for different rates waves. Synchronisation very short time ultra wide bandwidth reflectometer tokamak plasma pulse its easy configuration is then discussed. To simplify remotely operate system an Ethernet Lab View application software has been...