B.K. Shukla
A5051886497- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Gyrotron and Vacuum Electronics Research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Geophysics and Sensor Technology
- Nuclear Physics and Applications
- Real-Time Systems Scheduling
- Nuclear reactor physics and engineering
- Vacuum and Plasma Arcs
- Radio Astronomy Observations and Technology
- Particle Detector Development and Performance
- Iterative Learning Control Systems
- Pulsed Power Technology Applications
- Acoustic Wave Resonator Technologies
- Ionosphere and magnetosphere dynamics
- Microwave Engineering and Waveguides
- Soil Moisture and Remote Sensing
- Heat Transfer and Boiling Studies
- Parallel Computing and Optimization Techniques
- Heat Transfer and Optimization
- Superconducting and THz Device Technology
- Japanese History and Culture
Institute for Plasma Research
2014-2024
Several experiments, related to controlled thermonuclear fusion research and highly relevant for large size tokamaks, including ITER, have been carried out in ADITYA, an ohmically heated circular limiter tokamak. Repeatable plasma discharges of a maximum current ~160 kA discharge duration beyond ~250 ms with flattop ~140 obtained the first time ADITYA. The reproducibility has improved considerably lithium wall conditioning, are by precisely controlling position plasma. In these discharges,...
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...
A steady state superconducting tokamak (SST-1) has been commissioned after the successful experimental and engineering validations of its critical sub-systems. During 'engineering validation phase' SST-1; cryostat was demonstrated to be leak-tight in all operational scenarios, 80 K thermal shields were uniformly cooled without regions 'thermal runaway hot spots', toroidal field magnets their nominal conditions charged up 1.5 T at major radius. The further assembled SST-1 machine shell a...
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...
This paper summarizes the results of recent dedicated experiments on disruption control and runaway mitigation carried out in ADITYA, which are utmost importance for successful operation large size tokamaks, such as ITER. It is quite a well-known fact that disruptions tokamaks must be avoided. Disruptions, induced by hydrogen gas puffing, successfully avoided two innovative techniques ADITYA using bias electrode placed inside last closed flux surface applying an ion cyclotron resonance pulse...
RF systems in the ion cyclotron resonance frequency (ICRF) range and electron (ECRF) are an advanced stage of commissioning, to carry out pre-ionization, breakdown, heating current drive experiments on steady-state superconducting tokamak SST-1. Initially 1.5 MW continuous wave ICRF system would be used heat SST-1 plasma 1.0 keV during a pulse length 1000 s. For different scenarios at 3.0 T, wide band operating frequencies (20–92 MHz) is required. To meet this requirement two CW rf...
A 42-GHz electron cyclotron resonance heating (ECRH) system will be used to carry out preionization and start-up experiments on tokamaks SST-1 Aditya. The would give reliable in the tokamak at 1.5-T operating toroidal magnetic field. fundamental O-mode launched from low-field side of tokamak. same Aditya second-harmonic ECRH-assisted breakdown 0.75-T operation. gyrotron capable delivering 500-kW power installed such that it deliver both without dismantling any component. An approximately...
The 42-GHz electron cyclotron resonance heating (ECRH) system on SST-1 is used to carry out ECRH-assisted preionization, breakdown, start-up, and experiments at 0.75-T (second harmonic) 1.5-T (fundamental operation. gyrotron delivers 500-kW power frequency −50-kV beam voltage, 20-A current, 19-kV anode voltage. has been commissioned successfully dummy load for full parameters (500 kW/500 ms). transmission line consists of matching optic unit, circular corrugated waveguide, miter bend with...
In SST-1, 42GHz ECRH system has been commissioned to carry out breakdown and heating experiments at 0.75T 1.5T operating toroidal magnetic fields. The consists of high power microwave source Gyrotron capable deliver 500kW for 500ms duration, approximately 20 meter long transmission line a mirror based launcher. in fundamental O-mode & second harmonic X-mode is launched from low field side (radial port) the tokamak. At operation, 300 kW ECH successful assisted achieved loop_voltage ~ 3V....
Abstract In fusion devices, various techniques are employed for coating the plasma facing components (PFCs) including vessel wall with low-Z material like lithium, boron, and silicon in order to enhance parameters control. ADITYA-Upgrade tokamak, different of lithium conditioning developed implemented obtain uniform sustainable Li on PFCs wall. this paper, two used generate from source reported. one technique, a heated (fixed temperature ∼120 °C) Li-rod is placed inside hydrogen glow...
Electron Cyclotron Resonance Heating (ECRH) system will play an important role in plasma formation, heating and current drive the Superconducting Steady state Tokamak (SST-1). Commissioning activity of machine has been initiated. Many sub-systems have prepared for first discharge. A radial a top port allotted low field side (LFS) high (HFS) launch O X- modes plasma.
The design and characterization of a high-power microwave launcher have been discussed. launchers designed for electron cyclotron resonance heating the plasma in Steady-State Superconducting Tokamak (SST-1). High-power beam mainly consist focusing mirror plane combination to focus at specified location. Two are fabricated launch waves from low magnetic field side (radial port) as well high (top port). frequency operation is 82.6 GHz, power 200 kW/continuous wave. A gyrotron capable...
High-power tests on chemical vapor deposited (CVD) diamond window are carried out using 82.6-GHz Gyrotron. To test CVD with calorimetric dummy load, a matching optic unit is designed and fabricated special profiled mirrors. The mirrors by Gycom Russia mirror box assembly at Institute for Plasma Research. cooled water. consists of four arc detectors the protection window. connected to load this box. alignment done during testing in pulsed condition. After achieving desired Gaussian pattern...
The simulation on propagation of microwave beam from one transverse plane to other is useful for applications like phase retrieval beams propagating another. wave expansion method used paraxial a given field structure. This decomposes the arbitrary distribution in infinite number waves covering entire range directions axis. an extension Fourier transform concept where any signal decomposed into frequency components with ranging -infin +infin. One can easily propagate form by its components....
Silicon drift detector based X-ray spectrometer diagnostic was developed to study the non-thermal electron for Aditya tokamak plasma. The mounted on a radial mid plane port at Aditya. objective of includes estimation temperature ohmically heated Bi-Maxwellian plasma model adopted estimation. Along with that high Z impurity line radiation from ECR pre-ionization experiments also aimed. performance and first experimental results new system are presented.
AbstractAbstractThe 82.6 GHz/200 kW and 42 GHz/500 electron cyclotron resonance heating (ECRH) systems will be used in Tokamak SST-1 to carry out preionization start-up experiments at 3.0- 1.5-T operation. The 82.6-GHz gyrotron system has been tested for continuous waves (1000-s duration) using a conventional high-voltage power supply pulsed operation (200 1 s) regulated supply. 42-GHz ECRH is (500 ms), which 1.5 T (fundamental harmonic) on 0.75 (second Aditya. circular corrugated...
A 42GHz ECRH system would be used to carry out pre-ionization and start-up experiments on Tokamaks SST-1 Aditya. The give reliable in Tokamak at 1.5T operating toroidal magnetic field. Fundamental O-mode launched from low field side of tokamak. same also Aditya second harmonic assisted breakdown 0.75T operation. Gyrotron capable deliver 500kW power installed such that it will both the tokamaks without dismantling any component. It achieved by using two waveguide switches transmission line....
The 42GHz Electron Cyclotron resonance Heating (ECRH) system is used in tokamaks Aditya and SST-1 to carry out ECRH related experiments at fundamental second harmonic. Gyrotron capable deliver 500kW power for 500ms duration commissioned tokamak hall ~75m long transmission line laid connect both the tokamaks. corrugated waveguide (φ63.5mm) based normal atmospheric pressure transmit HE11 mode. special feature of this that it consists two switches, which facilitates either without changing any...
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...
A Gyrotron capable of delivering 200kW power at 82.6 GHz has been installed for pre-ionization and heating experiments on SST1 tokamak. based Electron Cyclotron Resonance Heating (ECRH) system involves systematic operation different auxiliary supplies, crowbar unit water cooling system. Versa Module Europe (VME) Data Acquisition Control (DAC) designed implemented the gyrotron operation. Softwares have developed using VxWorks RTOS open source Tcl-Tk tool-kit, GNU C/C++ compiler Linux.
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...