[HTML][HTML] Divertor plasma opacity effects

AA Pshenov, AS Kukushkin, AV Gorbunov… - Nuclear Materials and …, 2023 - Elsevier
In high recycling and detached plasma regimes the recycling region largely defines the
properties of the whole scrape-off layer plasma by setting up the density and temperature …

[HTML][HTML] Development of the neutral model in the nonlinear MHD code JOREK: Application to E× B drifts in ITER PFPO-1 plasmas

SQ Korving, GTA Huijsmans, JS Park, A Loarte… - Physics of …, 2023 - pubs.aip.org
The prediction of power fluxes and plasma-wall interactions impacted by MHD processes
during ITER operation [disruption, Edge Localized Modes (ELMs), 3D magnetic fields …

[HTML][HTML] The interplay of controlling the power exhaust and the tungsten content in ITER

R Dux, A Loarte, C Angioni, D Coster, E Fable… - Nuclear Materials and …, 2017 - Elsevier
The main elements defining the tungsten content of an ITER plasma, ie the gross erosion,
the prompt redeposition and the transport in the H-mode edge transport barrier are reviewed …

Nitrogen-seeded divertor detachment in TCV L-mode plasmas

O Février, C Theiler, JR Harrison, CK Tsui… - Plasma Physics and …, 2020 - iopscience.iop.org
Most of the detachment experiments done to date on the tokamak à configuration variable
(TCV), both in standard and alternative divertor geometries, focused on L-mode integrated …

Self-consistent cross-field transport model for core and edge plasma transport

S Baschetti, H Bufferand, G Ciraolo, P Ghendrih… - Nuclear …, 2021 - iopscience.iop.org
A two-equation model to self-consistently determine cross-field fluxes in the edge and
scrape-off layer (SOL) region of diverted plasma is used to complete 2D mean-field edge …

Progress in edge plasma turbulence modelling—hierarchy of models from 2D transport application to 3D fluid simulations in realistic tokamak geometry

H Bufferand, J Bucalossi, G Ciraolo, G Falchetto… - Nuclear …, 2021 - iopscience.iop.org
This contribution presents the recent effort at CEA and French federation for fusion to
simulate edge plasma transport with the new code SOLEDGE3X. The latter can be used …

Core integrated simulations for the Divertor Tokamak Test facility scenarios towards consistent core-pedestal-SOL modelling

I Casiraghi, P Mantica, R Ambrosino… - Plasma Physics and …, 2023 - iopscience.iop.org
Deuterium plasma discharges of the Divertor Tokamak Test facility (DTT) in different
operational scenarios have been predicted by a comprehensive first-principle based …

Flush-mounted Langmuir probes in the WEST tokamak divertor

R Dejarnac, D Sestak, JP Gunn, M Firdaouss… - Fusion Engineering and …, 2021 - Elsevier
The design of the Langmuir probes for the lower divertor of the WEST tokamak is presented,
in which uncooled, tungsten-coated graphite targets were installed for the first phase of …

Physics basis for the divertor tokamak test facility

F Crisanti, R Ambrosino, MV Falessi, L Gabellieri… - Nuclear …, 2024 - iopscience.iop.org
This paper is dealing with the physics basis used for the design of the Divertor Tokamak Test
facility (DTT), under construction in Frascati (DTT 2019 DTT interim design report (2019)) …

SOLPS-ITER simulations of the TCV divertor upgrade

M Wensing, BP Duval, O Février, A Fil… - Plasma Physics and …, 2019 - iopscience.iop.org
The effect of the upcoming TCV divertor upgrade on the distribution of neutrals and the onset
of detachment is studied using 2D transport code simulations. The divertor upgrade is …