Physics basis for the first ITER tungsten divertor
On the eve of component procurement, this paper discusses the present physics basis for
the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining …
the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining …
An overview of the numerical methods for tokamak plasma equilibrium computation implemented in the NICE code
B Faugeras - Fusion engineering and design, 2020 - Elsevier
The code NICE (Newton direct and Inverse Computation for Equilibrium) enables to solve
numerically several problems of plasma free-boundary equilibrium computations in a …
numerically several problems of plasma free-boundary equilibrium computations in a …
Presentation of the new SOLPS-ITER code package for tokamak plasma edge modelling
Simulations of ITER divertor performance, geometry optimization and estimates of key
related parameters such as fuelling throughput have historically relied on the SOLPS …
related parameters such as fuelling throughput have historically relied on the SOLPS …
The JOREK non-linear extended MHD code and applications to large-scale instabilities and their control in magnetically confined fusion plasmas
JOREK is a massively parallel fully implicit non-linear extended magneto-hydrodynamic
(MHD) code for realistic tokamak X-point plasmas. It has become a widely used versatile …
(MHD) code for realistic tokamak X-point plasmas. It has become a widely used versatile …
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 …
Pedestal structure, stability and scalings in JET-ILW: the EUROfusion JET-ILW pedestal database
L Frassinetti, S Saarelma, G Verdoolaege… - Nuclear …, 2020 - iopscience.iop.org
Abstract The EUROfusion JET-ILW pedestal database is described, with emphasis on three
main issues. First, the technical aspects are introduced, including a description of the data …
main issues. First, the technical aspects are introduced, including a description of the data …
Validation of edge turbulence codes against the TCV-X21 diverted L-mode reference case
Self-consistent full-size turbulent-transport simulations of the divertor and scrape-off-layer
(SOL) of existing tokamaks have recently become feasible. This enables the direct …
(SOL) of existing tokamaks have recently become feasible. This enables the direct …
Core radiative collapse characterisation and integrated modelling in WEST plasmas
V Ostuni, J Morales, JF Artaud, C Bourdelle… - Nuclear …, 2022 - iopscience.iop.org
In the full tungsten environment of WEST, during its first phase of operation, around 25% of
the pulses exhibited a rapid central electron temperature collapse. In its first phase, WEST …
the pulses exhibited a rapid central electron temperature collapse. In its first phase, WEST …
Advancing fusion with machine learning research needs workshop report
D Humphreys, A Kupresanin, MD Boyer, J Canik… - Journal of Fusion …, 2020 - Springer
Abstract Machine learning and artificial intelligence (ML/AI) methods have been used
successfully in recent years to solve problems in many areas, including image recognition …
successfully in recent years to solve problems in many areas, including image recognition …
Assessment of ITER divertor performance during early operation phases
During the ITER design phase, the focus of ITER boundary plasma modeling activities has
been on divertor performance under baseline H-mode, fusion power operation (FPO) …
been on divertor performance under baseline H-mode, fusion power operation (FPO) …