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作者:K.A. Jadeja , S.B. Bhatt ...
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:K.A. Jadeja , H.C. Joshi
来源:[J].Fusion Engineering and Design(IF 0.842), 2019, Vol.148
摘要:Abstract(#br)Bayard-Alpert (BA) type hot cathode ionisation gauge is widely used to measure neutral pressure precisely in vacuum system below 10 −3 Torr pressure. Neutral pressure measurement in magnetic confinement fusion experiments is quite challenging for standard BA typ...
作者:K.A. Jadeja , K.M. Patel ...
来源:[J].Nuclear Fusion(IF 2.734), 2020, Vol.60 (3)
摘要:The effect of a periodic train of short gas-puff pulses on the rotation frequency and amplitude of drift-tearing modes has been studied in ADITYA/ADITYA-U tokamak. The short gas puffs, injecting approximately molecules of fuel gas (hydrogen at one toroidal location, are found to ...
作者:K.A. Jadeja , Kiran Patel ...
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:K.A. Jadeja , K.M. Patel ...
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:K.A. Jadeja , K.M. Patel ...
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:K.A. Jadeja , S.B. Bhatt ...
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...

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