A5058746855- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Atomic and Molecular Physics
- Plasma Diagnostics and Applications
- Ionosphere and magnetosphere dynamics
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
Eindhoven University of Technology
2021-2024
ITER
2023-2024
Dutch Institute for Fundamental Energy Research
2019
JOREK is a massively parallel fully implicit non-linear extended MHD code for realistic tokamak X-point plasmas. It has become widely used versatile studying large-scale plasma instabilities and their control developed in an international community. This article gives comprehensive overview of the physics models implemented, numerical methods applied solving equations studies performed with code. A dedicated section highlights some verification work done hierarchy different available...
The prediction of power fluxes and plasma-wall interactions impacted by MHD processes during ITER operation [disruption, Edge Localized Modes (ELMs), 3D magnetic fields applied for ELM control, etc.] requires models that include an accurate description the themselves, as well edge plasma interaction processes. In this paper, we report progress on improving physics in nonlinear extended code JOREK, which has capabilities to simulate response external fields, disruptions ELMs. model includes E...
Accumulation of heavy impurities in the tokamak core is detrimental for its performance and can lead to disruption plasma. In small medium-sized tokamaks effective neoclassical transport pedestal typically oriented radially inward. larger tokamaks—e.g., ITER—where temperature gradient higher density gradients are lower due need operate a radiative divertor regime, predicted be outwards. The models derived axisymmetric quasi-steady-state plasmas. Applied 3D magnetic fields, i.e., Resonant...
Abstract A fusion reactor divertor must withstand heat flux densities <10 MW m −2 . Additionally, it may have to millisecond pulses on the order of 0.5 30 MJ due (mitigated) edge-localized modes (ELM) occurring with 60 Hz. We investigate if these requirements can be met by capillary porous system (CPS) liquid lithium divertors (LLD). 3D-printed tungsten CPS targets were exposed in linear plasma device Magnum-PSI, deuterium discharges lasting 15 s, generating 1.5 16 , and T e ∼ eV....
To achieve a tolerable heat and particle flux to the divertor target of fusion reactors, so-called plasma detachment is essential be set up controlled. Impurity seeding facilitates achievement such regime, mostly due enhanced radiation led by excitation-relaxation cycle species. Little known about impurity-induced chemical processes occurring in region during operation. In this work, influence three different impurities, i.e., N2, Ar, He, on performance studied. do so, experimental campaigns...
In this work we investigate the effects induced by presence of nitrogen in a detached-like hydrogen plasmas linear plasma machine Magnum-PSI. Detachment has been achieved increasing background neutral pressure target chamber means H2/N2 puffing and two cases study have set up, i.e. at 2 4 Pa. Achieved ne are ITER-relevant above 1020 m−3 electron temperatures range 0.8–2 eV. A scan among five different N2/H2+N2 flux ratios seeded carried out, values 0, 5, 10, 15 20%. decrease while fraction...