Abstract
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 language | English (US) |
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Pages (from-to) | 255-270 |
Number of pages | 16 |
Journal | Plasma Physics and Controlled Fusion |
Volume | 40 |
Issue number | 2 |
DOIs | |
State | Published - 1998 |
All Science Journal Classification (ASJC) codes
- Nuclear Energy and Engineering
- Condensed Matter Physics