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The goal for advanced steady-state operation in ITER should be to demonstrate the operation of the plasma core for a steady-state fusion reactor. To accomplish this the authors must develop steady-state operating scenarios at high beta for high fusion power density, low auxiliary power requirements (Q{sub CD} {ge} 25, where Q{sub CD} {triple_bond}P fusion/P{sub CD} and P{sub DC} is the power required for sustaining the plasma current) for low recirculating power requirements, and at moderate safety factor (q{sub {psi}} {le} 4.5) to minimize the cost for the tokamak core of a steady-state demonstration power reactor based on the operating modes demonstrated in ITER. The key to achieving steady-state operation at high fusion power in ITER will be the development of operating scenarios with very high bootstrap current fractions (f{sub BS} {ge} 90%) in which the radial profile of the bootstrap current density is well aligned with that of the total plasma current density, and for which the MHD {beta}-limit exceeds {beta}{sub n}{sup *} = 0.05 T{minus}m/MA. They are in the process of developing such operating modes for ITER. In {section}1 they propose two advanced steady-state operating points; a preliminary operating point that was the basis for the MHD studies reportedmore » in {section}2, and a second operating point that has been optimized based on the authors studies to date. In {section}2 they present calculations indicating that the initial operating point is stable to MHD ballooning and low-n kink modes (with a conducting wall at r = 1.25a) up to {beta}{sub n}{sup *} {approx} 6 {times} 10{sup {minus}2} T {minus} m/MA. In {section}3 they present a free-boundary MHD equilibrium, and show that advanced steady-state operating modes are compatible with the ITER poloidal field system and diverter.« less |
