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• W744262246 abstract "Introduction: In the framework of the European Power Plant Conceptual Studies (PPCS) environmental, safety and economic aspects of a future power plant, called DEMO, are studied. Still many issues, such as geometrical size, pulsed or s teady state operation need to be addressed. In these proceedings we present results of ‘DEMO Physics Studies’ concerning the analysis of β-limits in tokamaks. A high β-limit is a necessary condition for a working tokamak reactor. However, instabilities associated with i deal internal and external modes limit the plasma beta. Therefore, stability-optimized pla sma profiles have to be found. Attractive steady-state scenarios should also be characteri zed by a high bootstrap contribution to the plasma current. And, the stability-optimized plasma profiles have to be consistent with possible heating and current drive scenarios in order to be r elevant for tokamak reactor scenarios. We present stability studies of basic plasma and conducting wall configurations for tokamak reactor scenarios, which have been performed with the equilibrium VMEC/NEMEC code [1] and the linear stability CASTOR FLOW code [2]. Ideal MHD stability limits are determined for pulsed and steady state scenarios with ad-hoc postulated pressure and q-profiles. Furthermore, the stabilization of n 1 ideal modes by infinitely-conducting walls is studied using a set of walls in a parameterized distance from the plasma surface. These investigations will form a basis for later resistive-wall studies. Advance d tokamak scenarios with reversed q-profiles which are ideal stable may be unstable because of r esistive coupled tearing modes. Therefore, the stability of these equilibria is also invest igated with respect to resistive modes. Furthermore, the bootstrap contribution to the plasma current is computed for all considered plasma configurations. In order to arrive at stable plasma sc enarios with optimized transport properties, the stability limit of a transport optimized eq uilibrium derived by the ASTRA code [3] is also analyzed. Equilibria with monotonic q-profile. Although steady state advanced scenarios with reversed q-profile are the preferred operation mode for a reactor, puls ed scenarios with conventional monotonic q-profile are admitted as a fall-back option. The ideal MHD sta bility of low-n modes and the bootstrap currents of equilibria with monotonic q-profile are studied using various pressure profiles. The geometrical and physical parameters are: major radius R0 = 8.14 m, minor radius a0 = 2.80 m, aspect ratio A = 2.91, elongation E = 1.71, triangularity Δ = 0.35, toroidal vacuum magnetic field B0 R0 = 5.70 T, total plasma current Ip = 21.95 MA, beta normalized βN = 3.59, safety factor at the magnetic axis qa = 1.36, safety factor at the plasma boundary qb = 4.07. The pressure, total current and bootstrap current pr ofiles are shown in Figs 1 and 2. The pressure profile A is a peaked ASDEX Upgrade-type profile with" @default.
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• W744262246 date "2006-01-01" @default.
• W744262246 modified "2023-10-18" @default.
• W744262246 title "Analysis of ß-limits in tokamak reactor scenarios" @default.
• W744262246 hasPublicationYear "2006" @default.
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