英国物理学会
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作者:J. Ghosh , P.K. Chattopadhyay ...
来源:[J].Nuclear Fusion(IF 2.734), 2014, Vol.54 (8)IOP
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...
作者:J. Ghosh , P.K. Chattopadhyay ...
来源:[J].Nuclear Fusion(IF 2.734), 2015, Vol.55 (6)IOP
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:J. Ghosh , P.K. Chattopadhyay ...
来源:[J].Nuclear Fusion(IF 2.734), 2017, Vol.57 (10)IOP
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:J. Ghosh , R.L. Tanna ...
来源:[J].Nuclear Fusion(IF 2.734), 2018, Vol.58 (7)IOP
摘要:Sawteeth oscillations are commonly observed in temporal profiles of temperatures in almost all tokamaks including ADITYA tokamak. In typical discharges of ADITYA, bursts of hard x-ray (HXR) due to interaction of runaway electrons (RE) with limiter, during sawteeth crash are regul...
作者:J. Ghosh , Rohit Kumar ...
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (11)IOP
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:J. Ghosh , Y.C. Saxena ...
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (11)IOP
摘要:The CIMPLE-PSI laboratory in India’s northeast corner has been engaged over the last decade in the development of advanced experimental systems for controlled plasma fusion-relevant plasma surface interaction (PSI) studies and material testing. The CIMPLE-PSI experimental de...
作者:J. Ghosh , R.L. Tanna ...
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (8)IOP
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:... R.L. Tanna , J. Ghosh , ADITYA Team
来源:[J].Nuclear Fusion(IF 2.734), 2019, Vol.59 (8)IOP
摘要:Iron (Fe) impurity behaviour in ADITYA tokamak plasma has been studied using Fe spectral line emissions in the vacuum ultra violet (VUV) wavelength range. A VUV survey spectrometer has been utilized to record spectral lines at 28.41 nm from Fe14+ , and 33.54 nm and 36.08 nm ...
作者:J. Ghosh , S. B. Bhatt ...
来源:[J].Plasma Science and Technology(IF 0.514), 2013, Vol.15 (2)IOP
摘要: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 effect on plasma performance. After the Li-coating, an increment of ~100 eV in plasma electron temperature has been ob...
作者:J. Ghosh , S. Banerjee ...
来源:[J].Nuclear Fusion(IF 2.734), 2013, Vol.53 (2)IOP
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...

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