S. Brezinsek

RF-Specific Tungsten Erosion and Global Transport in ITER under Neon Seeding

Atul Kumar, Dhyanjyoti Nath, W. Tierens, J. Lore et autres

Ion cyclotron radio-frequency heating (ICRH) is a key auxiliary heating system in ITER, but high-power RF operation can enhance plasma-material interactions through rectified RF sheath potentials on antenna structures and nearby plasma-facing components. We present the first predictive application of the STRIPE …

First wall erosion induced by charge-exchange neutrals on EAST

Rui Ding, Jin Guo, Lei Mu, Guoliang Xu et autres

Abstract Charge-exchange neutrals (CXNs), in particular of hydrogen isotopes deuterium and tritium, are expected to contribute notably to first wall erosion in future fusion reactors. To understand the CXN-induced first wall erosion under different discharge conditions in deuterium, dedicated experiments with a …

cn, de (code pays fourni par la source)

Application of the line shape measurements in the linear plasma device PSI-2 as a benchmark of hydrogen plasma chemistry

V. Kotov, M Sackers, O. Marchuk, M. Reinhart et autres

Source-dependent kinetic separation of H in tungsten by Doppler-shift-tuned LIBS

Rongxing Yi, G. Sergienko, Erik Wuest, Stefano Cipelli et autres

Retention of Hydrogen (H) isotopes in plasma-facing materials is a critical issue for nuclear safety and self-sufficiency in fusion devices operating with Deuterium-Tritium (DT) fuel mixture and tungsten (W) plasma-facing components. Its reliable detection, either in-situ or ex-situ, is of great importance …

de, it (code pays fourni par la source)

Tungsten erosion and scrape-off layer transport modelling in L-mode helium plasma discharges in ASDEX Upgrade

G. Alberti, E. Tonello, C. Tuccari, F. Mombelli et autres

Abstract Due to its unavoidable presence in thermonuclear DT plasmas and its peculiar effects on materials, investigation of the role of helium (He) in plasma–wall interaction (PWI) in current tokamaks is fundamental. In this work, PWI in L-mode He plasma discharges in …

it, ch, de, fi, gb (code pays fourni par la source)

Ex situ investigation of boron, hydrogen, and oxygen distributions on W7-X divertor surfaces using picosecond-LIBS under vacuum

W7-X Team, Huace Wu, Christoph Kawan, E. Wüst et autres

Quantitative, spatially resolved measurements of near-surface material composition on plasma-facing components (PFCs) are critical for interpreting plasma–wall interaction (PWI) driven impurity sources, assessing wall-conditioning performance, and providing model constraints for impurity migration and co-deposition in present-day magnetic confinement devices and future reactors. …

Investigating long-duration plasma operation with the international multi-machine CICLOP database

X. Litaudon, E. Lerche, O. Grulke, Christopher Thomas Holcomb et autres

Abstract Combined high-fusion performance and long-pulse operation is one of the key integration challenges for fusion energy development in magnetic devices. Addressing these challenges requires an integrated vision of physics and engineering aspects with the purpose of simultaneously increasing time duration and …

fr, jp, de, us, cn, kr, at, gb, se, ru (code pays fourni par la source)

Vision transformer based parameter estimation for 2D Kuramoto–Sivashinsky models using physics informed features

Torben Schmitz, D. Reiser, José Ignacio Robledo, S. Brezinsek

Abstract Bombarding a surface with ions can cause the development of surface nanostructures. There exists a continuum model to describe the evolution of such surfaces with a partial differential equation. This equation is of the Kuramoto–Sivashinsky (KS) type, which depends on several …

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Erosion and impurity migration modelling in neon-seeded plasma discharges in ITER with a full-tungsten wall

C. Baumann, H. Kumpulainen, J. Romazanov, S. Rode et autres

Abstract The present work investigates global tungsten erosion and transport in two neon-seeded ITER discharges under burning plasma conditions using three-dimensional Monte-Carlo simulations with the ERO2.0 code. The modelling considers toroidally-symmetric plasma backgrounds obtained with the SOLPS-ITER code package, which cover the …

us (code pays fourni par la source)

ERO2.0 study of impurity deposition on ITER diagnostic mirrors assuming different material mixes

S. Rode, C. Baumann, S. Brezinsek, A. Kirschner et autres

Ex situ investigation of boron, hydrogen, and oxygen distributions on W7-X divertor surfaces using picosecond-LIBS under vacuum

Huace Wu, C. Kawan, E. Wüst, S. Brezinsek et autres

Abstract Quantitative, spatially resolved measurements of near-surface material composition on plasma-facing components (PFCs) are critical for interpreting plasma–wall interaction (PWI) driven impurity sources, assessing wall-conditioning performance, and providing model constraints for impurity migration and co-deposition in present-day magnetic confinement devices and future …

de, cn (code pays fourni par la source)

The Divertor Tokamak Test facility research plan

G. Giruzzi, P Martin, Clemente Angioni, S. Brezinsek et autres

Abstract The Divertor Tokamak Test facility (DTT) is a device presently under construction at the ENEA site in Frascati (Italy) in the framework of a joint public/private partnership. It has been designed as a superconducting tokamak with breakeven class performance, with the …

fr, it, de, us, in, se, gb, gr (code pays fourni par la source)