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作者:... Moti Makwana , C.N. Gupta , Mahesh Kushwah
来源:[J].Fusion Engineering and Design(IF 0.842), 2019, Vol.146 (Pt B), pp.2083-2086
摘要:Abstract(#br)The Aditya tokamak has been upgraded to Aditya-U by changing it’s vacuum vessel from rectangular to circular to accommodate the diverter coil for shaped plasma. The 42 GHz ECRH (Electron Cyclotron Resonance Heating) system has been integrated with the tokamak. T...
作者:C.N. Gupta , R. Srinivasan
来源:[J].Fusion Engineering and Design(IF 0.842), 2015, Vol.100, pp.287-292
摘要:Abstract(#br)Steady State Superconducting Tokamak (SST-1) comprises of various copper and superconducting coils for generating magnetic field for initiation, providing equilibrium and shaping of plasma in tokamak. In this paper, an attempt is made to study the induced EMF in...
作者:V. Balakrishnan , C.N. Gupta , R.K. Sinha
来源:[J].Fusion Engineering and Design(IF 0.842), 2003, Vol.66, pp.809-813
摘要:Abstract(#br)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 high d i /d t is created for the required loop voltage. After the plasma breakdown the plasma current con...
作者:C.N. Gupta , V.K. Panchal ...
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (11)
摘要:The first Indian tokamak, ADITYA, operated for over two decades with a circular poloidal limiter, has been upgraded to a tokamak named ADITYA Upgrade (ADITYA-U) to attain shaped-plasma operations with an open divertor in single and double-null configurations. Experimental re...
作者:C.N. Gupta , P.K. Chattopadhyay ...
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (8)
摘要:In the ADITYA Upgrade tokamak, glow discharge wall conditioning (GDC) is performed regularly during the high-temperature plasma operation cycle using hydrogen (H) and helium (He) gases. H GDC is carried out after long durations (few hours) of plasma operations on every plasm...
作者:C.N. Gupta , K.A. Jadeja ...
来源:[J].Nuclear Fusion(IF 2.734), 2017, Vol.57 (10)
摘要: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 plasma current of ~1...
作者:C.N. Gupta , Chhaya Chavda ...
来源:[J].Nuclear Fusion(IF 2.734), 2015, Vol.55 (6)
摘要:This paper summarizes the results of recent dedicated experiments on disruption control and runaway mitigation carried out in ADITYA, which are of the utmost importance for the successful operation of large size tokamaks, such as ITER. It is quite a well-known fact that disr...
作者:C.N. Gupta , D.K. Sharma ...
来源:[J].Nuclear Fusion(IF 2.734), 2015, Vol.55 (10)
摘要:A steady state superconducting tokamak (SST-1) has been commissioned after the successful experimental and engineering validations of its critical sub-systems. During the ‘engineering validation phase’ of SST-1; the cryostat was demonstrated to be leak-tight in all operation...
作者:C.N. Gupta , S.B. Bhatt ...
来源:[J].Nuclear Fusion(IF 2.734), 2013, Vol.53 (2)
摘要: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 line (2p3p 3D3–2p3d 3F4) at 650.024 nm is used to investigate oxygen im...
作者:C.N. Gupta , C.V.S. Rao ...
来源:[J].Nuclear Fusion(IF 2.734), 2014, Vol.54 (8)
摘要:Disruptions, induced in Aditya tokamak by hydrogen gas puffing, are successfully mitigated through stabilization of magnetohydrodynamic (MHD) modes by applying a bias voltage to an electrode placed inside the last-closed flux surface prior to the gas injection. Above a thres...

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