D. Purohit

ORCID: 0000-0003-4660-6123
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About
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Research Areas
  • Particle accelerators and beam dynamics
  • Magnetic confinement fusion research
  • Gyrotron and Vacuum Electronics Research
  • Superconducting Materials and Applications
  • Pulsed Power Technology Applications
  • Nuclear reactor physics and engineering
  • Advanced Electrical Measurement Techniques
  • Nuclear Physics and Applications
  • Microwave Engineering and Waveguides
  • Fusion materials and technologies
  • Plasma Diagnostics and Applications
  • Thermal Analysis in Power Transmission
  • Power Line Communications and Noise
  • Acoustic Wave Resonator Technologies
  • Vibration and Dynamic Analysis
  • Real-Time Systems Scheduling
  • Iterative Learning Control Systems

Institute for Plasma Research
2004-2024

ITER
2011-2015

A 24 MW Electron Cyclotron (EC) system operating at 170 GHz and 3600 s pulse length is to be installed on ITER. The EC plant shall deliver 20 of this power the plasma for Heating Current Drive (H&CD) applications. designed initiation, central heating, current drive, profile tailoring, Magneto-hydrodynamic control (in particular, sawteeth Neo-classical Tearing Mode) in flat-top phase plasma. preliminary design review was performed 2012, which identified a need extended application...

10.1063/1.4908598 article EN Physics of Plasmas 2015-02-01

The transmission line (TL) subsystem associated with the ITER electron cyclotron heating and current drive system has reached conceptual design maturity. At this stage responsibility of finalizing been transferred from Organization to U.S. Domestic Agency. purpose TL is transmit microwaves generated by 170-GHz gyrotrons installed in radio-frequency building launchers located one equatorial four upper tokamak ports. Each consists evacuated HE11 waveguides, direct-current breaks, power...

10.13182/fst05-38 article EN Fusion Science & Technology 2011-05-01

The electron cyclotron (EC) system of ITER for the initial configuration is designed to provide 20MW RF power into plasma during 3600s and a duty cycle up 25% heating (co counter) non-inductive current drive, also used control MHD instabilities. EC being procured by 5 domestic agencies plus Organization (IO). F4E has largest fraction procurements, which includes 8 high voltage supplies (HVPS), 6 gyrotrons, ex-vessel waveguides (includes isolation valves diamond windows) all launchers, 4...

10.1051/epjconf/20158704004 article EN cc-by EPJ Web of Conferences 2015-01-01

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...

10.13182/fst04-a529 article EN Fusion Science & Technology 2004-06-01

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...

10.1109/sofe.2015.7482270 article EN 2015-05-01

The EC H&CD system of ITER tokamak is an essential tool for all the phases operation. Different levels power are required through plasma discharge: up to 6.7 MW assisting breakdown and burn through, 20 current drive saw‐teeth control from equatorial launcher NTM stabilization upper launchers. assistance characterized by a very low (if not negligible) RF absorption plasma. A significant level stray radiation may also arise partial due non‐optimal parameters and/or wrong injected polarization....

10.1063/1.3664955 article EN AIP conference proceedings 2011-01-01

In SST-1 and Aditya-U Tokamaks, two ECRH systems (42GHz-500kW 82.6GHz-200k) are used to carry out various experiments related assisted plasma start-up heating at fundamental second harmonic. The tokamak is operated 1.5T magnetic field 42GHz system has been extensively for heating. 82.6GHz could not be thoroughly due limitation in power as 200kW enough breakdown original 82.6GHz-200kW being upgraded terms of experiment higher power. Gyrotron 400kW tested successfully factory delivers 48kV...

10.1051/epjconf/202431302004 article EN cc-by EPJ Web of Conferences 2024-01-01

A 42GHz-500kW ECRH system [1-6] is used to carry out various experiments related plasma breakdown and ECR heating on tokamaks SST-1 Aditya-U. The has been upgraded with new anode modulator power supply launch two pulses simultaneously. In SST-1, routinely for at fundamental harmonic, approximately 150kW launched 70ms 150ms duration consistent start-up achieved in SST-1. the recent experiments, second EC pulse also flat-top heat plasma, some signatures are seen but more will be carried...

10.1051/epjconf/202327702005 article EN cc-by EPJ Web of Conferences 2023-01-01

To study electron cylotron resonance (ECR) breakdown and afterglow plasma in an experimental linear system, a pulsed microwave source with rapid rise fall of power is desired. A fast capability for ECR experiments has been designed tested performance the system. tetrode, controlled by modulator card, used as switch to initiate from conventional magnetron operating at 2.45 GHz. The typical time ∼3 μs ∼10 μs. Using this scheme realistic 800 W power, neutral gas achieved delay are observed...

10.1063/1.2671793 article EN Review of Scientific Instruments 2007-02-01

Ion Cyclotron Resonance Heating (ICRH) is a promising heating method for fusion device due to its localized power deposition profile, direct ion at high density, and established technology RF generation transmission low cost. For the same reason 1.5-Megawatt ICRH system developed indigenously steady state super-conducting tokamak (SST-1).

10.1088/1742-6596/208/1/012015 article EN Journal of Physics Conference Series 2010-02-01
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