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

Journal Article · · Nuclear Fusion
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  1. Institute for Plasma Research, Gandhinagar (India); Nirma University, Ahmedabad (India)
  2. Institute for Plasma Research, Gandhinagar (India); Homi Bhabha National Institute (HBNI), Mumbai (India)
  3. Institute for Plasma Research, Gandhinagar (India); Saurashtra University, Rajkot (India)
  4. Institute for Plasma Research, Gandhinagar (India)
  5. Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
  6. Institute for Plasma Research, Gandhinagar (India); Pandit Deendayal Energy University, Gandhinagar (India)
  7. Oak Ridge Associated Universities (ORAU), Oak Ridge, TN (United States)
  8. Univ. of California, Los Angeles, CA (United States)
  9. University of Petroleum and Energy Studies, Dehradun (India)
  10. Institute for Plasma Research, Gandhinagar (India); RK University, Rajkot (India)
  11. Institute for Plasma Research, Gandhinagar (India); ITER-India, Ahmedabad (India). Institute for Plasma Research
  12. Bhabha Atomic Research Centre (BARC), Visakhapatnam (India)
  13. Nirma University, Ahmedabad (India)
  14. Saha Institute of Nuclear Physics, Kolkata (India)
The ADITYA upgrade (ADITYA-U), a medium-sized (R0 = 75 cm, a = 25 cm) conventional tokamak facility in India, has been consistently producing experiments findings by usingcircular 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 D2 plasmas when compared to H2 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-H2 mixture, localized wall cleaning by electron cyclotron resonant plasma, and the development of machine learning-based disruption predictions, will be discussed in this paper.
Research Organization:
Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC02-09CH11466
OSTI ID:
2441287
Journal Information:
Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 11 Vol. 64; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

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