Simulations of steady-state scenarios for Tore Supra using the CRONOS code

Abstract

Scenarios of steady-state, fully non-inductive current in Tore Supra are predicted using a package of simulation codes (CRONOS). The plasma equilibrium and transport are consistently calculated with the deposition of power. The achievement of high injected energy discharges up to 1 GJ is shown. Two main scenarios are considered: a low density regime with 90% non-inductive current driven by lower hybrid waves—lower hybrid current drive (LHCD)—and a high density regime combining LHCD and ion cyclotron resonance heating with a bootstrap current fraction up to 25%. The predictive simulations of existing discharges are also reported.

Spectroscopic diagnostics of superthermal electrons with high-number harmonic EC radiation in tokamak reactor plasmas

“…One can expect the dependence of spectrum's slope with increasing frequency on the absolute value of the central temperature. We illustrate this effect on the example of a variation of the electron temperature profile around that obtained in [21] for selfconsistent modeling of plasma parameters in a DEMOtype tokamak, with the help of the CRONOS suit of codes [22] for plasma equilibrium and transport modeling. The results of such an analysis are shown in figures 1-4.…”

“…Note that comparison of the codes for calculation the power losses profiles was carried out in [25] and [26] for various representation of the effective magnetic field which is relevant to the existing practice of the 1D transport modeling of tokamak plasma (e.g., ASTRA [27] and CRONOS [22]). This field, B(ρ), is obtained from the 2D magnetic field, B(ρ,θ), as a function of the normalized toroidal flux through the magnetic surface, ρ, and poloidal angle, θ, by averaging over magnetic flux surface.…”

Comparative Analysis of Electron Cyclotron Radiation Power Losses in Tokamaks Ignitor and Iter

“…Это позволило расширить бенчмаркинг [11] на случай неоднородных профилей магнитного поля B(), которые рассчитыва-ются по результатам самосогласованного расчёта 2D-равновесия плазмы и 1D-транспорта. Этот бенчмаркинг включил сравнение кода CYNEQ с результатами кода RAYTEC для заданных профилей T e () и n e (), а также сравнение с кодами CYTRAN и EXACTEC для профилей плазмы, включая профиль плотности тока, полу-ченных при самосогласованном 1.5D-моделировании транспорта плазмы [9,21,22] с помощью кодов АСТРА и CRONOS [23] соответственно. Такое сравнение позволило оценить влияние эффектов равновесия плазмы (сдвига Шафранова, 2D-профиля основных параметров плазмы) на профиль P EC ().…”

Integrated scenario in JET using real-time profile control

“…For the design of multi-input multi-output controller for real time profile control, let us first consider the layout of a general control system for tokamak as In this process, the plasma transfer functions (or kernel) K(s) is most of the time unknown, but can be identified either from power modulation experiments or by simulation using a predictive transport code such as CRONOS [40] or JETTO [41]. From this model, the coefficients of G(s) can be determined either by try and error simulation or using experimental techniques like the Ziegler-Nichols method [42].…”