Abstract:METIS is a numerical code aiming at fast full tokamak plasma analyses and predictions. It combines 0-D scaling-law normalised heat and particle transport with 1-D current diffusion modelling and 2-D equilibria. It contains several heat, particle and impurities transport models, as well as heat, particle, current and momentum sources, which allow faster than real time scenario simulations. This paper gives a first comprehensive description of the METIS suite: overall structure of the code, main available models… Show more
“…We perform interpretative integrated modelling using METIS [16] to compensate the lack of measurements inherent to newly operating tokamaks as is the case for WEST. METIS is a fast integrated tokamak modelling tool combining 0D scaling laws for kinetic profiles with 1D current diffusion modelling and 2D equilibria.…”
Section: Integrated Modelling and Data Consistency Using Metismentioning
Tungsten transport is investigated in WEST long pulse L-mode plasmas operated with the strike point on the actively cooled upper tungsten divertor. The pulses are mostly heated by lower hybrid waves. It is experimentally found that tungsten does not centrally accumulate throughout these ∼ 30 s reproducible discharges despite large normalised electron density gradients R/Ln e. To explain these observations, turbulent and neoclassical transport of electrons and tungsten ions are computed with GKW [1] and NEO [2, 3] respectively. Additionally, interpretative integrated modelling simulations are also performed to keep data coherency despite the lack of measurements of some quantities such as the Ti profiles. Modelled R/Ln e are found consistent with interferometry inversions and the tungsten peaking factor R/Ln W remains comparable to R/Ln e due to dominant turbulent diffusivities inside r/a = 0.3−0.8. In the central region r/a < 0.3 neoclassical W transport dominates but the convective velocities are several order of magnitudes lower compared to plasmas with toroidal rotation velocities induced by a neutral beam injection (NBI) torque. Finally, nitrogen is seeded in these pulses leading to an enhanced energy content which is consistent with stabilised ion temperature gradient modes from dilution.
“…We perform interpretative integrated modelling using METIS [16] to compensate the lack of measurements inherent to newly operating tokamaks as is the case for WEST. METIS is a fast integrated tokamak modelling tool combining 0D scaling laws for kinetic profiles with 1D current diffusion modelling and 2D equilibria.…”
Section: Integrated Modelling and Data Consistency Using Metismentioning
Tungsten transport is investigated in WEST long pulse L-mode plasmas operated with the strike point on the actively cooled upper tungsten divertor. The pulses are mostly heated by lower hybrid waves. It is experimentally found that tungsten does not centrally accumulate throughout these ∼ 30 s reproducible discharges despite large normalised electron density gradients R/Ln e. To explain these observations, turbulent and neoclassical transport of electrons and tungsten ions are computed with GKW [1] and NEO [2, 3] respectively. Additionally, interpretative integrated modelling simulations are also performed to keep data coherency despite the lack of measurements of some quantities such as the Ti profiles. Modelled R/Ln e are found consistent with interferometry inversions and the tungsten peaking factor R/Ln W remains comparable to R/Ln e due to dominant turbulent diffusivities inside r/a = 0.3−0.8. In the central region r/a < 0.3 neoclassical W transport dominates but the convective velocities are several order of magnitudes lower compared to plasmas with toroidal rotation velocities induced by a neutral beam injection (NBI) torque. Finally, nitrogen is seeded in these pulses leading to an enhanced energy content which is consistent with stabilised ion temperature gradient modes from dilution.
“…In the panel (a), the toroidal flux function is depicted, while the panel (b) shows the kinetic pressure, the density and the safety factor q. pressure on-axis is 1.0768 × 10 6 Pa, the flux function F on-axis is 12.95 Vs, while the density is 2.0739 × 10 20 m −3 . The normalized density profile has been obtained by studies of plasma scenario formation using the fast transport simulation code METIS (Artaud et al 2018).…”
Section: Application Of Falcon To a Dtt Scenariomentioning
confidence: 99%
“…The normalized density profile has been obtained by studies of plasma scenario formation using the fast transport simulation code METIS (Artaud et al. 2018). Figure 2.Plots of the main profiles for the DTT reference scenario.…”
Section: Application Of To a Dtt Scenariomentioning
In this work, the FALCON code is adopted for illustrating the features of shear Alfvén and sound continuous spectra in toroidal fusion plasmas. The FALCON codes employ the local Floquet analysis discussed in (Phys. Plasmas, vol. 26, issue 8, 2019, 082502) for computing global structures of continuous spectra in general toroidal geometry. As particular applications, reference equilibria for the divertor tokamak test and ASDEX Upgrade plasmas are considered. In particular, we illustrate the importance of mode polarization for recognizing the physical relevance of the various branches of the continuous spectra in the ideal magnetohydrodynamics limit. We also analyse the effect of plasma compression and the validity of the slow sound approximation.
“…Major radius R 0 and minor radius r a (m) 2.89, 0.94 Central magnetic eld B 0 (T ) The quasi-static magnetic eld and the thermal plasma properties were calculated in the framework of EUROfusion integrated modelling (EU-IM) using the METIS code which is described in [32]. To determine the input temperature and density proles, METIS uses tted JET experimental data from CRONOS tting tools [33], using the high resolution thomson scattering (HRTS) for the electron and density temperature proles, the charge exchange (CX) for the ion temperature prole and the visible spectroscopy (KS3) for the Z ef f prole.…”
Auxiliary heating is essential to initiate fusion in future tokamaks. In particular, ion heating tends to maximize the alpha power generation by increasing the thermal ion temperature. In order to simulate the plasma heating by Ion Cyclotron Radio Frequency waves (ICRF), the EVE code, a full-wave code for IC wave propagation, and SPOT, an orbit following Monte-Carlo code combined with the RFOF library which calculates the absorption of wave by ions, have been coupled together. This new package is used for simulating JET plasmas with strong interplay between ICRH and NBI (Neutral Beam Injection). Simulations shows that up to 20% of the neutron rate generated in recent JET D plasmas is due to the synergy between both heating mechanisms. However, the H concentration plays a critical role on such interplay, as beyond 2%, the synergy eciency weakens. Therefore, the control of the H concentration is mandatory for optimizing the fusion reaction rate generation at JET.
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