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Nuclear Fusion, ISSN 0029-5515, 06/2017, Volume 57, Issue 10, p. 102008
Several experiments, related to controlled thermonuclear fusion research and highly relevant for large size tokamaks, including ITER, have been carried out in... 
ADITYA tokamak | energy confinement time | disruption | neon gas puff | tokamak | enhanced plasma parameters | position control | LIMITS | PHYSICS, FLUIDS & PLASMAS | POWER | HEATING ASSISTED STARTUP | IMPROVED CONFINEMENT | DISCHARGES | DENSITY | RADIATIVE IMPROVED MODE | TRANSPORT
Journal Article
Fusion Engineering and Design, ISSN 0920-3796, 11/2017, Volume 124, pp. 558 - 561
Limiter based ADITYA tokamak has been upgraded in the divertor configured ADITYA-U tokamak. The ADITYA tokamak upgradation includes the replacement of... 
ADITYA tokamak | UHV | Vacuum vessel | Divertor | Limiter | NUCLEAR SCIENCE & TECHNOLOGY | Ports | Coils | Plasma | Dimensional measurement | Field coils | Vacuum technology | Tokamak devices | Radio frequency | Toruses | Heating | Coiling | Acceptance tests | Cross sections | Baking
Journal Article
NUCLEAR FUSION, ISSN 0029-5515, 08/2019, Volume 59, Issue 8, p. 86005
In the ADITYA Upgrade tokamak, glow discharge wall conditioning (GDC) is performed regularly during the high-temperature plasma operation cycle using hydrogen... 
tokamak | hydrogen recycling | PHYSICS, FLUIDS & PLASMAS | pulsed GDC
Journal Article
Nuclear Fusion, ISSN 0029-5515, 05/2018, Volume 58, Issue 7, p. 76004
Sawteeth oscillations are commonly observed in temporal profiles of temperatures in almost all tokamaks including ADITYA tokamak. In typical discharges of... 
runaway | MHD | ADITYA tokamak | runaway transport | sawtooth | plasma | PHYSICS, FLUIDS & PLASMAS | MAGNETIC RECONNECTION | NONTHERMAL ELECTRONS | TEXTOR | DISCHARGES
Journal Article
Nuclear Fusion, ISSN 0029-5515, 06/2015, Volume 55, Issue 6, pp. 63010 - 5
This paper summarizes the results of recent dedicated experiments on disruption control and runaway mitigation carried out in ADITYA, which are of the utmost... 
runaway | ICRH | control | electrode biasing | disruption | ECRH | PHYSICS, FLUIDS & PLASMAS | STABILIZATION | MODE | UPGRADE | PHYSICS, NUCLEAR | DISCHARGES | Electrodes | Databases | Hydrogen | Tokamak devices | Disruption | Magnetic fields | Electric fields | Avoidance
Journal Article
Nuclear Fusion, ISSN 0029-5515, 08/2014, Volume 54, Issue 8, pp. 83023 - 5
Disruptions, induced in Aditya tokamak by hydrogen gas puffing, are successfully mitigated through stabilization of magnetohydrodynamic (MHD) modes by applying... 
mode locking | tokamaks | magnetic confinement | resistive MHD modes | MHD ACTIVITY | MAGNETIC ISLANDS | PHYSICS, FLUIDS & PLASMAS | SUPPRESSION | Electrodes | Magnetohydrodynamics | Voltage | MHD | Tokamak devices | Disruption | Gas injection | Magnetic fields
Journal Article
Nuclear Fusion, ISSN 0029-5515, 02/2013, Volume 53, Issue 2, p. 23006
Intense visible lines from Be-like oxygen impurity are routinely observed in the Aditya tokamak. The spatial profile of brightness of a Be-like oxygen spectral... 
TRANSITION | TFTR TOKAMAK | ALCATOR C-MOD | PHYSICS, FLUIDS & PLASMAS | FLUCTUATIONS | ION | PHYSICS, NUCLEAR | TURBULENCE | SIMULATIONS | SCRAPE-OFF-LAYER | PLASMA ROTATION | ASDEX
Journal Article
Measurement Science and Technology, ISSN 0957-0233, 10/2014, Volume 25, Issue 10, pp. 105903 - 11
An experimental set-up to investigate the effect of a biased electrode introduced in the edge region on ADITYA tokamak discharges is presented. A specially... 
tokamaks | MHD modes | magnetized plasmas | silicon controlled rectifier | L-H transition | pulsed power supply | TCABR TOKAMAK | MAGNETIC ISLANDS | SUPPRESSION | DISCHARGES | POLOIDAL ROTATION | INSTRUMENTS & INSTRUMENTATION | ENGINEERING, MULTIDISCIPLINARY | CONFINEMENT | TURBULENCE | EDGE | PLASMA ROTATION | Electrodes | Confinement | Semiconductors | Electronics | Exposure | Tokamak devices | Disruption | Arrays | Density
Journal Article
Fusion Engineering and Design, ISSN 0920-3796, 11/2014, Volume 89, Issue 11, pp. 2659 - 2665
This visible light computerized tomography exercise is a part of a project to establish an auxiliary imaging method to assist other imaging facilities at the... 
Adaptive algorithm | Plasma diagnostics | Visible light tomography | ALGORITHMS | NUCLEAR SCIENCE & TECHNOLOGY | RECONSTRUCTION | CT imaging | Diagnostic imaging | Algorithms | Research institutes | Sensors | Mechanical engineering | Errors | Maximization | Imaging | Tomography | Projection | Ports | Tokamak devices | Entropy
Journal Article
MEASUREMENT SCIENCE AND TECHNOLOGY, ISSN 0957-0233, 11/2014, Volume 25, Issue 11
Journal Article
Physics of Plasmas, ISSN 1070-664X, 07/2010, Volume 17, Issue 7, pp. 072515 - 072515-7
In Aditya tokamak [ S. B. Bhatt Indian J. Pure Appl. Phys. 27 , 710 ( 1989 ) ], an increase in the H α and C 2 + intensity fluctuations from the edge region is... 
TURBULENCE | PLASMA | PHYSICS, FLUIDS & PLASMAS | MODE | PLASMA DENSITY | VARIATIONS | PLASMA INSTABILITY | INSTABILITY | ADITYA TOKAMAK | PLASMA DRIFT | HYDRODYNAMICS | MAGNETOHYDRODYNAMICS | PLASMA WAVES | TOKAMAK DEVICES | FLUID MECHANICS | MECHANICS | 70 PLASMA PHYSICS AND FUSION TECHNOLOGY | ALFVEN WAVES | CLOSED PLASMA DEVICES | FLUCTUATIONS | HYDROMAGNETIC WAVES | EMISSION | THERMONUCLEAR DEVICES
Journal Article
Measurement Science and Technology, ISSN 0957-0233, 11/2014, Volume 25, Issue 11, p. 119601
Journal Article
Journal of Physics: Conference Series, ISSN 1742-6588, 2012, Volume 390, Issue 1, pp. 12012 - 6
In the Aditya Tokamak, one of primary requirement for plasma generation is to feed the required quantity of the fuel gas prior to plasma shot. Gas feed system... 
Electric potential | Serial interfaces | Voltage | Pulse generators | Valves | Tokamak devices | Shot | Plasma (physics) | Standards
Conference Proceeding
等离子体科学和技术:英文版, ISSN 1009-0630, 2013, Volume 15, Issue 2, pp. 123 - 128
Lithiumization of the vacuum vessel wall of the Aditya tokamak using a lithium rod exposed to glow discharge cleaning plasma has been done to understand its... 
壁挂空调 | 辉光放电清洗 | 氢气回收 | 性能改善 | 能量约束时间 | 等离子体性能 | 托卡马克等离子体 | Aditya tokamak | Lithiumization | Impurity | Wall conditioning | wall conditioning | impurity | lithiumization | PHYSICS, FLUIDS & PLASMAS | DIII-D TOKAMAK | DISCHARGES | Reduction | Impurities | Lithium | Tokamak devices | Iron | Coating | Conditioning | Recycling | Walls
Journal Article
Physics of Plasmas, ISSN 1070-664X, 09/2010, Volume 17, Issue 9, pp. 092504 - 092504-6
Negative spikes followed by positive ones in the loop voltage signal during the discharge are observed in the Aditya Tokamak [ S. B. Bhatt , Indian J. Pure... 
Journal Article
Physics of Plasmas, ISSN 1070-664X, 12/1997, Volume 4, Issue 12, pp. 4292 - 4300
Vortex-like coherent structures are observed in the edge plasma of ohmically heated ADITYA tokamak [ Phys. Rev. Lett. 69, 1375 (1992)]. The structures are... 
BOUNDARY-LAYER | TRANSPORT | MAGNETIZED PLASMA | PHYSICS, FLUIDS & PLASMAS | FLUCTUATIONS | SPECTRA | K UF PHYSICS, FLUIDS & PLASMAS | DRIFT-WAVE TURBULENCE | ASDEX
Journal Article
Fusion Engineering and Design, ISSN 0920-3796, 2003, Volume 66, pp. 809 - 813
Ohmic heating power supply is used in ADITYA Tokamak for plasma breakdown and current drive. Presently the ohmic coils store a magnetic flux of 0.40 V s and... 
ADITYA Tokamak | Plasma current | Feedback control | ADITYA tokamak | plasma current | NUCLEAR SCIENCE & TECHNOLOGY | feedback control
Journal Article
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