Nuclear Fusion (Jan 2024)

Plasma performance enhancement and impurity control using a novel technique of argon–hydrogen mixture fueled glow discharge wall conditioning in the ADITYA-U tokamak

  • K.A. Jadeja,
  • J. Ghosh,
  • K.M. Patel,
  • A.B. Patel,
  • R.L. Tanna,
  • Kiran Patel,
  • B.G. Arambhadiya,
  • K.D. Galodiya,
  • Rohit Kumar,
  • S. Aich,
  • Harshita Raj,
  • L. Pradhan,
  • M.B. Chowdhuri,
  • R. Manchanda,
  • N. Ramaiya,
  • Nandini Yadava,
  • Sharvil Patel,
  • Kajal Shah,
  • Dipexa Modi,
  • A. Gauttam,
  • K. Singh,
  • S. Dolui,
  • Ankit Kumar,
  • B. Hegde,
  • A. Kumawat,
  • Minsha Shah,
  • R. Rajpal,
  • U. Nagora,
  • P.K. Atrey,
  • S.K. Pathak,
  • Shishir Purohit,
  • A. Adhiya,
  • Manoj Kumar,
  • Kumudni Assudani,
  • D. Kumavat,
  • S.K. Jha,
  • K.S. Shah,
  • M.N. Makwana,
  • Shivam Gupta,
  • Supriya Nair,
  • Kishore Mishra,
  • D. Raju,
  • P.K. Chattopadhyay,
  • B.R. Kataria

DOI
https://doi.org/10.1088/1741-4326/ad6a6e
Journal volume & issue
Vol. 64, no. 10
p. 106048

Abstract

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Effective control of impurities and precise regulation of the fueling gas are supreme prerequisites for optimal operation in any fusion device. Conventional wall-conditioning methods fall short of achieving optimal wall conditioning. Conventional wall-conditioning methods, such as vessel baking and H _2 /(D _2 )-fueled glow discharge cleaning (GDC), are generally required to remove wall-absorbed impurities in bulk after vessel venting. The excess amount of hydrogen, injected during H _2 GDC, can be reduced by helium (He)-fueled GDC. However, He removal from the vessel is more challenging due to its low molecular mass, very low condensation temperature, and inert characteristics. In ADITYA-U, optimal wall conditioning cannot be achieved using H _2 followed by He-fueled GDC when applied for extended periods spanning hours or days. A GDC with a mixture of argon and hydrogen (Ar–H _2 ) is introduced in the ADITYA-U tokamak to obtain better wall conditioning than H _2 followed by He GDC. In Ar–H _2 GDC, long-lived ArH ^+ ions are formed in sufficient numbers and accelerated toward the vessel wall with high momentum. This results in the breaking of high energy bonds of impurities with the wall/plasma facing components, which is not possible by H ^+ , H _2 ^+, H _3 ^+ ions in H _2 GDC due to their lower momentum. An optimal blend ratio of Ar to H _2 is established at 15%–20% for the mixture. This composition ensures that the introduction of high- Z Ar does not adversely affect tokamak plasma operations. The C- and O-containing impurities are reduced beyond the limit of the prolonged operation of H _2 GDC. Relative low pressures of dominant impurities such as CO, CH _4 , and H _2 O are obtained due to the Ar–H _2 GDC compared to routinely operated H _2 GDC. A comparison study of H _2 GDC and the developed Ar–H _2 GDC is performed in terms of wall conditioning and tokamak plasma operation. The encouraging results of the Ar–H _2 GDC are obtained in both wall cleaning and tokamak operation scenarios in the midsize tokamak ADITYA-U. This development and application of Ar–H _2 GDC are beneficial for large-sized fusion devices, leading to improved impurity reduction, reduced operational fuel consumption (H _2 /D _2 /He), and enhanced control over fuel recycling/extraction.

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