[HTML][HTML] Development of the neutral model in the nonlinear MHD code JOREK: Application to E× B drifts in ITER PFPO-1 plasmas
The prediction of power fluxes and plasma-wall interactions impacted by MHD processes
during ITER operation [disruption, Edge Localized Modes (ELMs), 3D magnetic fields …
during ITER operation [disruption, Edge Localized Modes (ELMs), 3D magnetic fields …
Multi-machine SOLPS-ITER comparison of impurity seeded H-mode radiative divertor regimes with metal walls
SOLPS-ITER modelling databases of three tokamaks—ASDEX-Upgrade, JET and ITER with
fluid drifts activated are compared to understand the dependence of edge plasma …
fluid drifts activated are compared to understand the dependence of edge plasma …
Fast dynamic 1D simulation of divertor plasmas with neural PDE surrogates
Managing divertor plasmas is crucial for operating reactor scale tokamak devices due to
heat and particle flux constraints on the divertor target. Simulation is an important tool to …
heat and particle flux constraints on the divertor target. Simulation is an important tool to …
Overview of density pedestal structure: role of fueling versus transport
S Mordijck - Nuclear Fusion, 2020 - iopscience.iop.org
How much of the density pedestal structure is determined by fueling versus transport is still
an open question. In most current tokamaks, the scrape-off layer is not opaque enough to …
an open question. In most current tokamaks, the scrape-off layer is not opaque enough to …
Algorithmic Differentiation for adjoint sensitivity calculation in plasma edge codes
S Carli, L Hascoët, W Dekeyser… - Journal of Computational …, 2023 - Elsevier
In the framework of fusion energy research, divertor design and model calibration based on
plasma edge codes currently rely either on manual iterative tuning of parameters, or …
plasma edge codes currently rely either on manual iterative tuning of parameters, or …
Experimental study on the role of the target electron temperature as a key parameter linking recycling to plasma performance in JET-ILW
Abstract Changes in global and edge plasma parameters (H 98 (y, 2), dimensionless
collisionality ν*, core density peaking, separatrix density ne, sep) with variations in the D 2 …
collisionality ν*, core density peaking, separatrix density ne, sep) with variations in the D 2 …
H-mode plasmas in the pre-fusion power operation 1 phase of the ITER research plan
A Loarte, AR Polevoi, M Schneider, SD Pinches… - Nuclear …, 2021 - iopscience.iop.org
The optimum conditions for access to and sustainment of H-mode plasmas and their
expected plasma parameters in the pre-fusion power operation 1 (PFPO-1) phase of the …
expected plasma parameters in the pre-fusion power operation 1 (PFPO-1) phase of the …
Assessment of the impact of fuelling puff location on divertor impurity compression and enrichment in STEP
RT Osawa, SL Newton, D Moulton… - Nuclear …, 2024 - iopscience.iop.org
In order to achieve a compatible solution between the divertors and the core, SOLPS-ITER
simulations were performed in a Spherical Tokamak for Energy Production (STEP) …
simulations were performed in a Spherical Tokamak for Energy Production (STEP) …
High gas throughput SOLPS-ITER simulations extending the ITER database to strong detachment
SOLPS-ITER simulations performed for Q DT= 10, P SOL= 100 MW burning plasmas on
ITER extend the existing database to high values of separatrix averaged neon impurity …
ITER extend the existing database to high values of separatrix averaged neon impurity …
The role of edge fueling in determining the pedestal density in high neutral opacity Alcator C-Mod experiments
Abstract SOLPS-ITER modeling of EDA H-mode experiments on Alcator C-Mod find that the
electron density pedestal structure is unaffected by increased gas fueling when approaching …
electron density pedestal structure is unaffected by increased gas fueling when approaching …