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Overview of physics results from the ADITYA-U tokamak and future experiments

Authors :
R.L. Tanna
J. Ghosh
K.A. Jadeja
Rohit Kumar
Suman Aich
K.M. Patel
Harshita Raj
Kaushlender Singh
Suman Dolui
Kajal Shah
S. Patel
Nandini Yadava
Tanmay Macwan
A. Kanik
Ankit Kumar
Bharat Hegde
Ashok Kumawat
A. Kundu
R. Joshi
Deepti Sharma
Ankit Patel
L. Pradhan
K. Galodiya
Shwetang Pandya
Soumitra Banerjee
Sk Injamul Hoque
Komal
M.B. Chowdhuri
R. Manchanda
N. Ramaiya
Ritu Dey
G. Shukla
D. Modi
Vishal Sharma
Aman Gauttam
M.N. Makwana
Kunal Shah
S. Gupta
Supriya Nair
S. Purohit
U.C. Nagora
A. Adhiya
Kiran Patel
Kumudni Asudani
S.K. Jha
D. Kumawat
Santosh Pandya
Varsha S.
Praveenlal Edappala
B. Arambhadiya
Minsha Shah
Pramila Gautam
V. Raulji
Praveena Shukla
Abhijeet Kumar
Mitesh Patel
R. Rajpal
M. Bhandarkar
Imran Mansuri
Kirti Mahajan
K. Mishra
Sunil Kumar
B.K. Shukla
Jagabandhu Kumar
P.K. Sharma
Snehlata Aggarwal
Kumar Ajay
M.K. Gupta
S.K. Pathak
P.K. Chattopadhyay
D. Raju
S. Dutta
S. Pahari
N. Bisai
Chetna Chauhan
Y.C. Saxena
A. Sen
R. Pal
S. Chaturvedi
Source :
Nuclear Fusion, Vol 64, Iss 11, p 112011 (2024)
Publication Year :
2024
Publisher :
IOP Publishing, 2024.

Abstract

The ADITYA upgrade (ADITYA-U), a medium-sized $\left( {{R_0} = 75{\text{ cm}},\,\,a = 25{\text{ cm}}} \right)$ conventional tokamak facility in India, has been consistently producing experiments findings by using circular and shaped-plasmas. Recognizing the plasma parameters aligning closely with the design parameters of circular limited plasmas, ADITYA-U shifted its focus toward exploring the operational regime for experimentation on saw-tooth and MHD phenomena. Moreover, ADITYA-U has made consistent advancements toward conducting preliminary plasma shaping experiments through the activation of top and bottom divertor coils utilizing hydrogen as well as deuterium fuels. Confinement is improved by a factor of ∼1.5 in ${D_2}$ plasmas when compared to H _2 plasmas of ADITYA-U. Further, ADITYA-U operations emphasize preventing disruptions and runaway electrons (REs) to ensure safe operations for future fusion devices. Significant suppression of REs has been achieved in ADITYA-U with the application of pulsed localized vertical magnetic field (LVF) perturbation, thereby establishing the technique’s independence from the tokamak device. The successful RE mitigation requires a critical threshold of LVF pulse magnitude, which is approximately 1% of the toroidal magnetic field, and a minimum duration of ∼5 ms. Apart from this, several novel findings have been achieved in the ADITYA-U experiments, including the modification of sawtooth duration through gas-puff, the emergence of MHD-induced geodesic acoustic mode-like oscillations, the propagation of fast heat pulses induced by MHD activity, the control of RE dynamics through Gas-puffs, the propagation of pinch-driven cold-pulses, the transport and core accumulations of argon impurities, the mass dependency of plasma toroidal rotation and the detection of ‘RICE’ scaling, as well as the characterization of edge plasma using wall conditioning methods, such as glow discharge cleaning using a combination of Ar -H _2 mixture, localized wall cleaning by electron cyclotron resonant plasma, and the development of machine learning-based disruption predictions, will be discussed in this paper.

Details

Language :
English
ISSN :
17414326 and 00295515
Volume :
64
Issue :
11
Database :
Directory of Open Access Journals
Journal :
Nuclear Fusion
Publication Type :
Academic Journal
Accession number :
edsdoj.3483c8e9383c49df9c6397ed9d21f62f
Document Type :
article
Full Text :
https://doi.org/10.1088/1741-4326/ad3c50