Yashashri Patil

ORCID: 0000-0003-0195-997X
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About
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Research Areas
  • Fusion materials and technologies
  • Nuclear Materials and Properties
  • Plasma Diagnostics and Applications
  • Advanced materials and composites
  • Metal and Thin Film Mechanics
  • Electrohydrodynamics and Fluid Dynamics
  • Magnetic confinement fusion research
  • Plasma Applications and Diagnostics
  • Nuclear reactor physics and engineering
  • Dust and Plasma Wave Phenomena
  • Ion-surface interactions and analysis
  • Intermetallics and Advanced Alloy Properties
  • Non-Destructive Testing Techniques
  • Metallurgical Processes and Thermodynamics
  • Tribology and Wear Analysis
  • Vacuum and Plasma Arcs
  • Metallurgical and Alloy Processes
  • Fire effects on concrete materials
  • Composite Structure Analysis and Optimization
  • Electron and X-Ray Spectroscopy Techniques
  • Thermography and Photoacoustic Techniques
  • Laser-Plasma Interactions and Diagnostics
  • Electronic Packaging and Soldering Technologies
  • Microwave-Assisted Synthesis and Applications
  • Integrated Circuits and Semiconductor Failure Analysis

Institute for Plasma Research
2011-2023

Homi Bhabha National Institute
2023

Jamia Millia Islamia
2020

The High Heat Flux Test Facility (HHFTF) was designed and established recently at Institute for Plasma Research (IPR) in India testing heat removal capability operational life time of plasma facing materials components the ITER-like tokamak. HHFTF is equipped with various diagnostics such as IR cameras IR-pyrometers surface temperature measurements, coolant water calorimetry absorbed power measurements thermocouples bulk measurements. capable simulating steady state load several MW m−2 well...

10.1088/0031-8949/t167/1/014020 article EN Physica Scripta 2016-01-12

The effect of a transverse magnetic field on spatial electron temperature Te distribution along the line joining center capacitively driven rectangular discharge plates, operated at 13.56 MHz in push-pull configuration, has been presented. It is found that almost uniform low operating pressure (1 Pa). However, as background increases, tends to peak near plates. overall magnitude also increase throughout volume account increasing pressure. This experimental observation qualitatively depicted...

10.1063/1.5118762 article EN Physics of Plasmas 2020-03-01

We investigate the discharge characteristics of a low-pressure geometrically asymmetric cylindrical capacitively coupled plasma with an axisymmetric magnetic field generating E × B drift in azimuthal direction. Vital parameters, including electron density, temperature, DC self-bias, and energy probability function (EEPF), are studied experimentally for different strength (B) values. A transition parameters is observed specific range fields where highly efficient lower temperature. Outside...

10.1063/5.0160506 article EN Physics of Plasmas 2023-09-01

Abstract This paper is focused on various aspects of the development and testing water cooled divertor PFCs. Divertor PFCs are mainly designed to absorb heat particle fluxes outflowing from core plasma fusion devices like ITER. The First Wall Technology Development Division at Institute for Plasma Research (IPR), India, extensively working facing components (PFCs). Tungsten graphite macro-brush type test mock-ups were produced using vacuum brazing furnace technique tungsten monoblock...

10.1515/nuka-2015-0053 article EN cc-by-nc-nd Nukleonika 2015-06-01

This work shows the development of a volume-produced negative ion source that consists annular parallel plates driven by 13.56 MHz capacitively coupled radio frequency in push-pull configuration. advantages controlling plasma conditions varying pressure, power, and applied axial magnetic field. It is found configuration allows potential to remain range 20 40 Volts. Conversely, application field helps serves augment production ions central hollow part plate. Further, plausible explanation...

10.48550/arxiv.2406.13506 preprint EN arXiv (Cornell University) 2024-06-19

The dielectric constant of a sheath, whether ionic or electronic, formed around the cylindrical limbs hairpin probe, is often considered same as that vacuum. However, this assumption does not hold true for electron sheaths and electron-permeating sheaths, resulting in deviation sheath from This significantly influences effective between limbs. As result, it impacts theoretically estimated resonance frequency characteristic curve DC-biased probe. In study, we investigate influence temperature...

10.48550/arxiv.2406.13497 preprint EN arXiv (Cornell University) 2024-06-19

This work investigates the discharge properties of a cylindrical magnetized capacitive coupled plasma produced between pair coaxial cylinders. For purpose diagnosing and electron energy distribution function (EEDF), an in-house electronic circuit RF-compensated Langmuir probe are devised constructed. The second harmonic technique (SHT) has been applied to obtain direct measurement EEDF evaluated effect RF magnetization on bulk heating within discharge. external magnetic field overall rise in...

10.48550/arxiv.2412.08155 preprint EN arXiv (Cornell University) 2024-12-11

Tungsten (W) monoblocks of the Plasma Facing Unit (PFU) are exposed to inhomogeneous heat loads arises due exponentially decaying power flux along Scrap Layer (SOL) away from separatrix as well fabrication tolerances and misalignment divertor targets in poloidal toroidal directions. Thermal structural analysis a tungsten monoblock under such need be investigated. The paper presents results Finite Element Analysis (FEA) performed on loaded by surface 10 MW/m2 plasma wetted area 4 shaded with...

10.1088/1742-6596/823/1/012022 article EN Journal of Physics Conference Series 2017-04-19

The plasma facing components (PFCs) inside a tokamak are typically exposed to extremely high heat flux of the order MW/m(2). brazing quality between materials (PFMs) and sink will determine structural integrity hence effective service life these PFCs. Suitable non-destructive testing (NDT) techniques for pre-qualification thus essential evaluate their at various stages life. Macro-brush type mockups prototype PFCs with graphite as PFM have been inspected using different active Infrared...

10.1063/1.4940728 article EN Review of Scientific Instruments 2016-02-01

Divertor is a plasma facing component of tokamak such as ITER Tokomak.Divertor mainly designed to remove the heat flux and particle escaping from core region into Scrape Off Layer tokomak.Inner& Outer vertical targets Dome are components Divertor.Tungsten most promising material joined with copper alloy sink in various geometries.Inner & divertor made tungsten tiles arranged monoblock geometry fabricated straight well curved shape.Total 260000 numbers monoblocks will be used device having...

10.21611/qirt.2015.0024 article EN 2015-01-01

Plasma Facing Components (PFCs) are made of Tungsten, Copper & CuCrZr heat sink, with casting on Tungsten. Due to vast difference in thermal expansion coefficients (15.4*10 <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">-6</sup> 4.5*10 per xmlns:xlink="http://www.w3.org/1999/xlink">0</sup> K) between Tungsten and it is proposed have an interlayer W/Cu Functionally Graded Material (FGM) Copper. Present work investigates the effects introduced...

10.1109/sofe.2013.6635437 article EN 2013-06-01

We investigate the discharge characteristics of a low-pressure geometrically asymmetric cylindrical capacitively coupled plasma with an axisymmetric magnetic field generating EXB drift in azimuthal direction. Vital parameters, including electron density, temperature, DC self-bias, and Electron Energy distribution function (EEDF), are studied experimentally for varying strength (B). A transition asymmetry is observed along range fields where highly efficient lower temperature. Outside this...

10.48550/arxiv.2306.00594 preprint EN cc-by arXiv (Cornell University) 2023-01-01

Laboratory plasma experiments serve as an essential tool for mimicking complicated phenomena seen in space and at the plasma-material interface encountered industrial fusion applications. The parameter aforementioned medium typically ranges from extremely low densities (10 <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">8</sup> particles m xmlns:xlink="http://www.w3.org/1999/xlink">-3</sup> ) to high n <inf...

10.1109/iceaa57318.2023.10297658 article EN 2022 International Conference on Electromagnetics in Advanced Applications (ICEAA) 2023-10-09
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