Design and first applications of the ITER integrated modelling & analysis suite
F Imbeaux, SD Pinches, JB Lister, Y Buravand… - Nuclear …, 2015 - iopscience.iop.org
Abstract The ITER Integrated Modelling & Analysis Suite (IMAS) will support both plasma
operation and research activities on the ITER tokamak experiment. The IMAS will be …
operation and research activities on the ITER tokamak experiment. The IMAS will be …
Metis: a fast integrated tokamak modelling tool for scenario design
JF Artaud, F Imbeaux, J Garcia, G Giruzzi, T Aniel… - Nuclear …, 2018 - iopscience.iop.org
METIS is a numerical code aiming at fast full tokamak plasma analyses and predictions. It
combines 0D scaling-law normalised heat and particle transport with 1D current diffusion …
combines 0D scaling-law normalised heat and particle transport with 1D current diffusion …
Divertor heat flux challenge and mitigation in SPARC
Owing to its high magnetic field, high power, and compact size, the SPARC experiment will
operate with divertor conditions at or above those expected in reactor-class tokamaks …
operate with divertor conditions at or above those expected in reactor-class tokamaks …
Stability optimization of energetic particle driven modes in nuclear fusion devices: the FAR3d gyro-fluid code
The development of reduced models provide efficient methods that can be used to perform
short term experimental data analysis or narrow down the parametric range of more …
short term experimental data analysis or narrow down the parametric range of more …
Nonlinear ELM simulations based on a nonideal peeling–ballooning model using the BOUT++ code
A minimum set of equations based on the peeling–ballooning (P–B) model with nonideal
physics effects (diamagnetic drift, E× B drift, resistivity and anomalous electron viscosity) is …
physics effects (diamagnetic drift, E× B drift, resistivity and anomalous electron viscosity) is …
ELM control with RMP: plasma response models and the role of edge peeling response
Resonant magnetic perturbations (RMP) have extensively been demonstrated as a
plausible technique for mitigating or suppressing large edge localized modes (ELMs) …
plausible technique for mitigating or suppressing large edge localized modes (ELMs) …
Three-dimensional modeling of plasma edge transport and divertor fluxes during application of resonant magnetic perturbations on ITER
Results from three-dimensional modeling of plasma edge transport and plasma–wall
interactions during application of resonant magnetic perturbation (RMP) fields for control of …
interactions during application of resonant magnetic perturbation (RMP) fields for control of …
Prediction of divertor heat flux width for ITER using BOUT++ transport and turbulence module
Investigation of turbulent transport dynamics in scrape-off-layer (SOL) and divertor heat flux
width prediction is performed for ITER. Both BOUT++ transport and BOUT++ turbulence …
width prediction is performed for ITER. Both BOUT++ transport and BOUT++ turbulence …
A comparison of the impact of central ECRH and central ICRH on the tungsten behaviour in ASDEX Upgrade H-mode plasmas
A comparison of the impact of additional central electron cyclotron resonance heating
(ECRH) and ion cyclotron resonance heating (ICRH) on the behaviour of the tungsten (W) …
(ECRH) and ion cyclotron resonance heating (ICRH) on the behaviour of the tungsten (W) …
The role of the source versus the collisionality in predicting a reactor density profile as observed on ASDEX Upgrade discharges
E Fable, C Angioni, V Bobkov, J Stober, R Bilato… - Nuclear …, 2019 - iopscience.iop.org
The design and optimization of a future tokamak fusion reactor, from the point of view of the
plasma performance and output fusion power, requires the understanding of the underlying …
plasma performance and output fusion power, requires the understanding of the underlying …