Zobrazeno 1 - 10
of 27
pro vyhledávání: '"B.R. Kadia"'
Autor:
Ashok K. Sinha, Pradip Kumar Jain, K.M. Parmar, Narendra Kr. Singh, Y.S.S. Srinivas, Mukesh Kumar Alaria, Sanjay V. Kulkarni, Subrato Das, B.R. Kadia, Nalini Pareek, Udaybir Singh, Nitin Kumar, Anirban Bera, K. Satynaryana, Alok Mishra, Rajan Babu, D. Rathi, Atul Varia, Hasina Khatun, M. V. Kartikeyan, Mitesh Kevadia, Shreeniwas Joshi, Om Ranjan, Vishant
Publikováno v:
IEEE Transactions on Plasma Science. 47:4658-4663
A 42-GHz, 200-kW gyrotron was developed and tested for the Indian plasma fusion system. The gyrotron was designed for the TE0,3 operating mode. The configuration of the triode-type magnetron injection gun (MIG) with the linear RF output, undepressed
Publikováno v:
Fusion Engineering and Design. 138:226-230
Many high power RF amplifiers, working at various frequencies are being used in ICRH group. High power RF output is obtained by amplification in stages i.e. 50 W, 2 kW, 20 kW, 200 kW. These stages are connected as chain and act as driver for the fina
Autor:
Siju George, Prashant L Thankey, S.K. Patnaik, Minsha Shah, H. Nimavat, Dilip C Raval, Kirit Vasava, Mainak Bandyopadhyay, Debjyoti Basu, Sudhir Kumar Sharma, Yuvakiran Paravastu, K. A. Jadeja, D. Raju, M.V. Gopalakrishna, Pramila Gautam, Sneha P Jayaswal, Ruby Trivedi, D. Rathi, Manoj Patel, B.R. Kadia, Raj Singh, Kalpesh R Dhanani, Aparajita Mukherjee, Paresh Vasava, Ajesh Subbarao, Vijaykumar N Patel, K.M. Parmar, Chirag Bhavsar, Ziauddin Khan
Publikováno v:
Plasma Physics and Controlled Fusion. 64:015004
In general, superconducting tokamaks require low loop voltage current start-up for the safety purpose of their poloidal field coils. The loop voltage inside the vacuum vessel of Steady State Superconducting Tokamak (SST-1) is low in nature since its
Autor:
D. Bhattacharya, D. Bora, H M Jadav, Raghuraj Singh, Y.S.S. Srinivas, Aparajita Mukharjee, P. Biswas, B.R. Kadia, Rajnish Kumar, Anil Bhardwaj, Agrajit Gahlot
Publikováno v:
Fusion Engineering and Design. 82:853-859
A 1.5 MW ion cyclotron resonance heating (ICRH) system is being developed as an auxiliary heating system for steady state super-conducting tokamak-1 (SST-1) plasma. Different frequencies between 20 and 91.2 MHz have been selected to allow second harm
Autor:
M. Harsha, Sanjay V. Kulkarni, B.R. Kadia, P.L. Khilar, S. Dani, H. Patel, H M Jadav, D. Bora, Jai Prakash Soni, P. Shah, K. G. Parmar, A.R. Makwana, Y.S.S. Srinivas, D. Rathi, Mahesh Kushwah, Ashish Patel, B. K. Shukla, S. Gangopadhyay, P. Kirit, K. Sathyanarayana, C. G. Virani, B. Pal, Richa Trivedi, S. Rajashree, Anil Bhardwaj
Publikováno v:
Fusion Science and Technology. 50:551-560
An electron cyclotron resonance heating system is commissioned on Aditya tokamak to carry out preionization, start-up, and heating experiments. A high-power microwave source (gyrotron), capable of delivering 200-kW cw power at 28 ± 0.1 GHz, is commi
Autor:
Rajan Babu, K. Sathyanarayana, H M Jadav, Rajnish Kumar, Mikhail Shmelev, D. Pragnesh, P. Biswas, D. Bhattacharya, Jai Prakash Soni, Manoj Kumar Singh, P. Dharmesh, B. K. Shukla, Y.S.S. Srinivas, A. K. Bhardwaj, Singh Raghuraj, D. Bora, P. Kirit, H. Patel, P. Jatin, V. I. Belousov, B.R. Kadia, P.L. Khilar, R. Sugandhi, G. Siju, Raj Singh, G. Agrajit, K.M. Parmar, Asmita Mukherjee, E. M. Tai, S.V. Kulkarni, Sunil Kumar, V. K. Yadav, V. Kurbatov, D. Rathi, Mahesh Kushwah, M. Harsha, S. Dani, A.R. Makwana, Prabal K. Chattopadhyay, Atul Varia, C. G. Virani, Yu. Belov, J. P. Singh
Publikováno v:
Nuclear Fusion. 46:S72-S84
RF systems in the ion cyclotron resonance frequency (ICRF) range and electron cyclotron resonance frequency (ECRF) range are in an advanced stage of commissioning, to carry out pre-ionization, breakdown, heating and current drive experiments on the s
Autor:
Suresh Adav, Varghese K Dr.George, S.R. Sanjeev Kumar, D. Rathi, D. Bhattacharya, H. Machhar, Asmita Mukherjee, H M Jadav, Raguraj Singh, S.V. Kulkarni, Rajnish Kumar, S. Dani, Sunil Kumar, D. Bora, K.M. Parmar, J. P. Singh, Mahesh Kushwah, P. Shah, A. K. Bhardwaj, Ashfaq Patel, Raj Singh, Sukanya Gangopadhyay, Y.S.S. Srinivas, B.R. Kadia, P.L. Khilar
Publikováno v:
Sadhana. 30:21-46
An ion cyclotron resonance heating (ICRH) system has been designed, fabricated indigenously and commissioned on Tokamak Aditya. The system has been commissioned to operate between 20.0 and 47.0 MHz at a maximum power of 200 kW continuous wave (CW). D
Autor:
B.R. Kadia, P.L. Khilar, D. Bora, P. Dharmesh, Manoj Kumar Singh, Mikhail Shmelev, A.R. Makwana, P. Biswas, V. I. Belousov, Chetan, K. G. Parmar, Kumar Rajnish, Y.S.S. Srinivas, P. Kirit, Rajan Babu, E. M. Tai, P. Jatin, B. K. Shukla, R. Sugandhi, V. Kurbatov, Yu. Belov, Jignesh Soni, Vipin K. Yadav, Mahesh Kushwah, K. Sathyanarayana, M. Harsha, G. Agrajit, Prabal K. Chattopadhyay, Harshida Patel, D. Pragnesh
Publikováno v:
Journal of Physics: Conference Series. 25:96-102
Electron Cyclotron Resonance Heating (ECRH) system will play an important role in plasma formation, heating and current drive in the Superconducting Steady state Tokamak (SST-1). Commissioning activity of the machine has been initiated. Many of the s
Autor:
K. Sathyanarayana, B. Jadav, Pankaj Sharma, Kumar Rajnish, P.R. Parmar, Y.S.S. Srinivas, K.M. Parmar, B.R. Kadia, P.L. Khilar, S. L. Rao, Kartick K. Samanta, G. Verghese, Suhas Kulkarni, M. Jha, S. Gangopadhyay, S. Dani, Ashish Patel, Paulami Shah, Mahesh Kushwah, D. Bora, K.G. Parmar, S. Raghuraj, Rajesh Trivedi
Publikováno v:
Fusion Engineering and Design. :575-579
A Lower Hybrid Current Drive (LHCD) system would be the prime method to drive current in SST-1. The LHCD system is based upon two TH2103D klystrons of M/s Thomson CSF at 3.7 GHz capable of delivering 500 kW CW microwave power. The klystrons have been
Autor:
H M Jadav, C. V. S. Rao, K. Mishra, Jiten Ghosh, R. K. Manchanda, B.R. Kadia, Raghavan Srinivasan, P. K. Kaw, Rajesh Singh, A. Gayatri, Y.S.S. Srinivas, S.V. Kulkarni, Y. S. Joisa, Aditya Team, R. Joshi, A K Chattopadhyaya, K.M. Parmar, D. Bora, Atul Varia, S. Dani, D. Rathi, S. B. Bhatt, S. Kumar, R. A. Yogi, P K Chattopadhyaya, C. N. Gupta, R. K. Jha, Man Singh, P. K. Atrey
Publikováno v:
AIP Conference Proceedings.
Fast wave electron heating experiments are carried out on Aditya tokamak [R = 0.75 m, a = 0.25m,Bt = 0.75T,ne∼1–3E13/cc,Te∼250eV] with the help of indigenously developed 200 kW, 20–40 MHz RF heating system. Significant direct electron heating