全部文献期刊会议图书|学者科研项目
中外文文献  中文文献  外文文献
作者:S.B. Bhatt , Kulav Rathod ...
来源:[J].Fusion Engineering and Design(IF 0.842), 2017
摘要:Abstract(#br)Limiter based ADITYA tokamak has been upgraded in the divertor configured ADITYA-U tokamak. The ADITYA tokamak upgradation includes the replacement of rectangular cross section vacuum vessel by circular cross section vacuum vessel to accommodate additional poloi...
作者:S.B. Bhatt , Ajai Kumar ...
来源:[J].Fusion Engineering and Design(IF 0.842), 2005, Vol.75, pp.655-661
摘要:Abstract(#br)Plasma density control is a prime requirement of tokamak plasma. Various methods are used for fuelling the gas for tokamak plasma. Gas fuelling in tokamak with molecular beam injection is developed for efficient gas injection during the plasma discharge. The pen...
作者:S.B. Bhatt , K. Sathyanarayana ...
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:S.B. Bhatt , M.B. Chowdhuri ...
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:S.B. Bhatt , V.K. Panchal ...
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:S.B. Bhatt , C.N. Gupta ...
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:S.B. Bhatt , Y.C. Saxena
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:S.B. Bhatt , P.K. Atrey ...
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...

我们正在为您处理中,这可能需要一些时间,请稍等。

资源合作:cnki.scholar@cnki.net, +86-10-82896619   意见反馈:scholar@cnki.net

×