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Flux-driven integrated modelling of main ion pressure and trace tungsten transport in ASDEX Upgrade

TLDR
In this paper, the quasilinear gyrokinetic code QuaLiKiz is applied for successful predictions of core kinetic profiles in an ASDEX Upgrade H-mode discharge in the turbulence dominated region within the integrated modelling suite JETTO.
Abstract
Neoclassical and turbulent heavy impurity transport in tokamak core plasmas are determined by main ion temperature, density and toroidal rotation profiles. Thus, in order to understand and prevent experimental behaviour of W accumulation, flux-driven integrated modelling of main ion heat and particle transport over multiple confinement times is a vital prerequisite. For the first time, the quasilinear gyrokinetic code QuaLiKiz is applied for successful predictions of core kinetic profiles in an ASDEX Upgrade H-mode discharge in the turbulence dominated region within the integrated modelling suite JETTO. Neoclassical contributions are calculated by NCLASS; auxiliary heat and particle deposition profiles due to NBI and ECRH are prescribed from previous analysis with TRANSP. Turbulent and neoclassical contributions are insufficient in explaining main ion heat and particle transport inside the q  =  1 surface, necessitating the prescription of further transport coefficients to mimic the impact of MHD activity on central transport. The ion to electron temperature ratio at the simulation boundary at p tor=0.85 stabilizes ion scale modes while destabilizing ETG modes when significantly exceeding unity. Careful analysis of experimental measurements using Gaussian process regression techniques is carried out to explore reasonable uncertainties. In following trace W impurity transport simulations performed with additionally NEO, neoclassical transport under consideration of poloidal asymmetries alone is found to be insufficient to establish hollow central W density profiles. Reproduction of these conditions measured experimentally is found possible only when assuming the direct impact of a saturated (m, n) = (1, 1) MHD mode on heavy impurity transport.

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Journal Article

Plasma wall interaction and its implication in an all tungsten divertor tokamak. Invited Paper

R. Neu, +156 more
TL;DR: In this article, it was found that the large He content in the plasma, resulting from DC glow discharges for conditioning, leads to a confinement reduction and after the change to D glow for inter-shot conditioning, the He content quickly dropped and, in parallel, the usual H-mode confinement with H factors close to one was achieved.

Poloidal variation of high-Z impurity density due to hydrogen minority ion cyclotron resonance heating on Alcator C-Mod

TL;DR: In this paper, a parallel high-Z impurity transport theory is extended to account for cyclotron effects and shown to agree with experimentally measured impurity density asymmetries.
Journal ArticleDOI

Fast modeling of turbulent transport in fusion plasmas using neural networks

TL;DR: In this paper, an ultrafast neural network model, QLKNN, was proposed to predict core tokamak transport heat and particle fluxes, based on a database of 3'×'108 flux calculations of the quasilinear gyrokinetic transport model, QuaLiKiz.
Journal ArticleDOI

Predictions of core plasma performance for the SPARC tokamak

TL;DR: In this article, the authors present a detailed analysis of expected turbulence regimes with linear and nonlinear CGYRO simulations, demonstrating that profile predictions with the TGLF reduced model are in reasonable agreement.
References
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Journal ArticleDOI

Steady-state radiative cooling rates for low-density, high-temperature plasmas

TL;DR: For 47 elements in the range 2 ≤ Z ≤ 92, steady-state radiative cooling rates, average charge states, and mean square charge states have been calculated for low-density, high-temperature plasmas (n e ≲ 10 16 electrons/cm 3 and T = 0.002-100 keV) as discussed by the authors.
Journal ArticleDOI

The tokamak Monte Carlo fast ion module NUBEAM in the National Transport Code Collaboration library

TL;DR: The NUBEAM module as mentioned in this paper is a comprehensive computational model for Neutral Beam Injection (NBI) in tokamaks, which is used to compute power deposition, driven current, momentum transfer, fueling, and other profiles.
Journal ArticleDOI

Bootstrap current and neoclassical transport in tokamaks of arbitrary collisionality and aspect ratio

TL;DR: In this article, a multi-species fluid model is described for the steady state parallel and radial force balance equations in axisymmetric tokamak plasmas, and the bootstrap current, electrical resistivity and particle and heat fluxes are evaluated in terms of the rotation velocities and friction and viscosity coefficients.
Journal ArticleDOI

Tungsten as material for plasma-facing components in fusion devices

TL;DR: In this paper, the use of tungsten (W) as material for plasma-facing components (PFM) in fusion devices is reviewed with respect to its plasma and material compatibility under burning plasmas conditions.
Journal ArticleDOI

Materials for the plasma-facing components of fusion reactors

TL;DR: In this article, the authors show that the performance of tungsten surfaces under intense transient thermal loads is another critical issue, since the formation of a melt layer may favor the generation of highly activated dust particles.
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