Numerical analysis of helium ash removal by using ICRH-driven ripple transport

K. Hamamatsu, C. S. Chang, T. Takizuka, M. Azumi, T. Hirayama, S. Cohen, T. Tani

Research output: Contribution to journalArticlepeer-review

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Helium ash removal across the last closed flux surfaces in a deuterium-tritium fuelled tokamak plasma is studied using an orbit-following Monte Carlo simulation. Ripple transport of helium ash ions is induced by ion cyclotron resonance heating (ICRH) of short-lived He+ ions, which are produced by charge exchange of He2+ with incoming neutral species. It is found that the required ICRH power in an ITER grade tokamak plasma is 10-15 MW and the helium transport to the first wall is localized within an area given by 1.3 m in the toroidal direction and 0.7 m in the poloidal direction.

Original languageEnglish (US)
Pages (from-to)255-270
Number of pages16
JournalPlasma Physics and Controlled Fusion
Issue number2
StatePublished - 1998

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Condensed Matter Physics


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