【摘要】：The Ohmically heated circular limiter tokamak ADITYA(R_0?=?75 cm, a?=?25 cm) has been upgraded to a tokamak named the ADITYA Upgrade(ADITYA-U) with an open divertor configuration with divertor plates. The main goal of ADITYA-U is to carry out dedicated experiments relevant for bigger fusion machines including ITER, such as the generation and control of runaway electrons, disruption prediction, and mitigation studies, along with an improvement in confinement with shaped plasma. The ADITYA tokamak was dismantled and the assembly of ADITYA-U was completed in March 2016. Integration of subsystems like data acquisition and remote operation along with plasma production and preliminary plasma characterization of ADITYA-U plasmas are presented in this paper.
R L TANNA;J GHOSH;Harshita RAJ;Rohit KUMAR;Suman AICH;Vaibhav RANJAN;K A JADEJA;K M PATEL;S B BHATT;K SATHYANARAYANA;P K CHATTOPADHYAY;M N MAKWANA;K S SHAH;C N GUPTA;V K PANCHAL;Praveenlal EDAPPALA;Bharat ARAMBHADIYA;Minsha SHAH;Vismay RAULJI;M B CHOWDHURI;S BANERJEE;R MANCHANDA;D RAJU;P K ATREY;Umesh NAGORA;J RAVAL;Y S JOISA;K TAHILIANI;S K JHA;M V GOPALKRISHANA;;Plasma production and preliminary results from the ADITYA Upgrade tokamak[J];Plasma Science and Technology;2018年07期