P. K. Chattopadhyay

ORCID: 0009-0008-6886-2789
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Research Areas
  • Magnetic confinement fusion research
  • Plasma Diagnostics and Applications
  • Particle accelerators and beam dynamics
  • Ionosphere and magnetosphere dynamics
  • Dust and Plasma Wave Phenomena
  • Laser-Plasma Interactions and Diagnostics
  • Fusion materials and technologies
  • Superconducting Materials and Applications
  • Food composition and properties
  • Laser-induced spectroscopy and plasma
  • Food Drying and Modeling
  • Agricultural Engineering and Mechanization
  • Gyrotron and Vacuum Electronics Research
  • Atomic and Molecular Physics
  • Semiconductor Quantum Structures and Devices
  • Inorganic and Organometallic Chemistry
  • Solar and Space Plasma Dynamics
  • Electrohydrodynamics and Fluid Dynamics
  • Rice Cultivation and Yield Improvement
  • Earthquake Detection and Analysis
  • Chemical Thermodynamics and Molecular Structure
  • GABA and Rice Research
  • Quantum Dots Synthesis And Properties
  • Nuclear physics research studies
  • Plant Physiology and Cultivation Studies

Institute for Plasma Research
2016-2025

Homi Bhabha National Institute
2019-2025

Plasma (Macedonia)
2012

Indian Institute of Technology Kharagpur
1999-2009

Maharshi Dayanand University
1985-2007

University of Wisconsin–Madison
1999-2005

University of California, Los Angeles
2002

Saha Institute of Nuclear Physics
1996-2000

Goethe University Frankfurt
1993

Panjab University
1991

10.1006/jaer.2000.0664 article EN Journal of Agricultural Engineering Research 2001-10-01

Experiments on ADITYA-U tokamak show a marked enhancement in the sawtooth period by application of short gas puffs fuel that cause modification radial density profile. A consequent suppression trapped electron modes (TEMs) then leads to an increase core temperature. This slows down heat propagation following crash, causing delay achieving critical temperature gradient inside q = 1 surface required for next crash happen. The overall scenario has strong similarities with behavior under...

10.48550/arxiv.2501.01871 preprint EN arXiv (Cornell University) 2025-01-03

Experimental observations of the intrinsic excitation and non-linear interactions drift wave (DW) Kelvin–Helmholtz (KH) instabilities in a linear magnetized plasma column are presented. The experiments carried out inverse mirror experimental device (IMPED)—a cylindrical, magnetized, machine designed to study low-frequency waves plasma. A novel feature IMPED is ability control profiles, such as density n(r), electron temperature Te(r), potential Vp(r) by varying ratio Rm magnetic field main...

10.1063/5.0250606 article EN cc-by-nc-nd Physics of Plasmas 2025-02-01

An innovative instrumentation technique is developed to enable precise and efficient positional scans with motorized probe diagnostics, distributed axially radially in Inverse Mirror Plasma Experimental Device (IMPED). The system automates diagnostic operations by positioning the probes, triggering conditioning circuits, acquiring archiving structured data. A client–server based architecture implemented into discrete hierarchical layers enabling remote operation control over Ethernet...

10.1063/5.0244966 article EN Review of Scientific Instruments 2025-03-01

Reduction of core-resonant m=1 magnetic fluctuations and improved confinement in the Madison Symmetric Torus [Dexter et al., Fusion Technol. 19, 131 (1991)] reversed-field pinch have been routinely achieved through control surface poloidal electric field, but it is now known that has limited part by edge-resonant m=0 fluctuations. Now, refined field control, plus toroidal possible to reduce simultaneously This allowed high-energy runaway electrons, possibly indicative flux-surface...

10.1063/1.1456930 article EN Physics of Plasmas 2002-05-01

ADVERTISEMENT RETURN TO ISSUEPREVArticleNEXTSolvent dependence of ligand substitution kinetics nickel(II)P. K. Chattopadhyay and J. F. CoetzeeCite this: Inorg. Chem. 1973, 12, 1, 113–120Publication Date (Print):January 1973Publication History Published online1 May 2002Published inissue 1 January 1973https://pubs.acs.org/doi/10.1021/ic50119a028https://doi.org/10.1021/ic50119a028research-articleACS PublicationsRequest reuse permissionsArticle Views213Altmetric-Citations47LEARN ABOUT THESE...

10.1021/ic50119a028 article EN Inorganic Chemistry 1973-01-01

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,...

10.1088/1741-4326/aa6452 article EN Nuclear Fusion 2017-06-23

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...

10.1088/1741-4326/ab0a9e article EN Nuclear Fusion 2019-02-26

Improved confinement has been achieved in the MST through control of poloidal electric field, but it is now known that improvement limited by bursts an edge-resonant instability. Through refined field control, plus toroidal we have suppressed these bursts. This led to a total beta 15% and reversed-field-pinch-record estimated energy time 10 ms, tenfold increase over standard value which for first substantially exceeds scaling characterized most reversed-field-pinch plasmas.

10.1103/physrevlett.87.205001 article EN Physical Review Letters 2001-10-24

Energy confinement comparable with tokamak quality is achieved in the Madison Symmetric Torus (MST) reversed field pinch (RFP) at a high beta and low toroidal magnetic field. Magnetic fluctuations normally present RFP are reduced via parallel current drive outer region of plasma. In response, electron temperature nearly triples doubles. The time increases ten-fold (to ∼10 ms), which L- H-mode scaling values for same plasma current, density, heating power, size shape. Runaway evidenced by...

10.1088/0029-5515/43/12/014 article EN Nuclear Fusion 2003-12-01

Parboiled rice as well puffed kernels were examined using Scanning electron microscopy for studying the ultra-structural changes that take place during processes involved. transverse sections of polished parboiled grains revealed an approximately 0.1 mm thick peripheral endosperm layer. In this layer starch granules appeared swollen and embedded in a protein matrix, while those inner transformed into fused mass gelatinized starch. Transverse various stages cells expansion due to high...

10.1111/j.1745-4549.1990.tb00123.x article EN Journal of Food Processing and Preservation 1990-02-01

In the Helicon eXperimental (HeX) device, geometric aperture is fixed, but position of magnetic can be varied. Working with Argon gas in pressure range 1 − 10 × 4 mbar, an annular plasma (density ∼ 16 m 3) formed downstream, always front aperture. This occurs irrespective relative or presence a radial electric field. contrary to earlier proposition made by others that field necessary produce hollow profile. Instead, ionization neutrals radially outer region tail electrons, rotating fast due...

10.1063/1.4975665 article EN Physics of Plasmas 2017-02-01

The result of adding the spin density term in heavy-ion interaction potentials is studied for first time, especially unclosed shell nuclei. For energy functional Skyrme interaction, contribution derived nuclei with an even number valence particles (or holes). calculations are made light nuclei, using both shell-model and Fermi-type nucleon densities. potential calculated proximity theorem, corrected Thomas-Fermi approximation kinetic density. Only repulsive found to be significant, which...

10.1103/physrevc.43.315 article EN Physical Review C 1991-01-01

The TCV tokamak facility is used to study the effect of innovative plasma shapes on core and edge confinement properties. In low collisionality L-mode plasmas with electron cyclotron heating (ECH) increases increasing negative triangularity δ. improvement correlates a decrease inner heat transport, even though vanishes core, pointing non-local transport has recently started effects in H-mode plasmas. known improve towards positive triangularity, due increase pedestal height, plagued by...

10.1585/pfr.7.2502148 article EN Plasma and Fusion Research 2012-01-01

Numerical modeling shows that localized, efficient current drive is possible in overdense toroidal plasmas (such as reversed field pinches and spherical tokamaks) using perpendicular launch of electron Bernstein waves. The wave directionality required for driving can be obtained by launching the waves above or below midplane torus a geometric effect related to poloidal magnetic field. Wave absorption strong, result electrostatic nature waves, giving suprathermal tail formation drive.

10.1063/1.873951 article EN Physics of Plasmas 2000-05-01

Views Icon Article contents Figures & tables Video Audio Supplementary Data Peer Review Share Twitter Facebook Reddit LinkedIn Tools Reprints and Permissions Cite Search Site Citation Manjit Kaur, Sayak Bose, P. K. Chattopadhyay, D. Sharma, J. Ghosh, Y. C. Saxena, Edward Thomas; Generation of multiple toroidal dust vortices by a non-monotonic density gradient in direct current glow discharge plasma. Phys. Plasmas 1 September 2015; 22 (9): 093702. https://doi.org/10.1063/1.4929916 Download...

10.1063/1.4929916 article EN Physics of Plasmas 2015-09-01

Disruptions, induced in Aditya tokamak by hydrogen gas puffing, are successfully mitigated through stabilization of magnetohydrodynamic (MHD) modes applying a bias voltage to an electrode placed inside the last-closed flux surface prior injection. Above threshold sheared Er × Bφ rotation plasma generated edge biasing leads substantial reduction growth MHD (m/n = 3/1, 2/1), which causes avoidance disruptions prevention mode overlapping and subsequent ergodization magnetic field lines.

10.1088/0029-5515/54/8/083023 article EN Nuclear Fusion 2014-06-26
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