29 June 2026 to 3 July 2026
EICC, Edinburgh
Europe/London timezone

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

Not scheduled
20m
EICC, Edinburgh

EICC, Edinburgh

150 Morrison St, Edinburgh EH3 8EE
Poster Presentation SOL, Divertor and PWI (MCF)

Description

The control of plasma-wall interactions (PWI) such as erosion and deposition of high-Z material, as well as the understanding of impurity migration are key challenges for stable operation of fusion devices. Plasma performance becomes critical once the core concentration of high-Z material is too high. To strengthen earlier findings in view of the change to a full tungsten (W) machine in the recent 2024 ITER re-baseline [1], and in support of impact estimates on burning plasma performance [2], refinement of the W source and influx assessments for a broad range of scenarios is an important exercise. Here, the 3D Monte-Carlo gyro-kinetic code ERO2.0 is applied to increase the sophistication of W erosion and subsequent migration simulations under both ion and charge-exchange neutral (CXN) impact.

This contribution presents an overview of the most-up-to-date ERO2.0 simulations of baseline neon (Ne)-seeded Q=10 H-mode plasmas for varying separatrix-averaged Ne concentrations. Plasma backgrounds for the simulations are provided by the latest wide-grid version of the SOLPS-ITER code, furnishing a much improved, self-consistent description of the scrape-off layer (SOL) plasma right up to the main chamber walls. Although CXN erosion is treated most accurately using bivariate energy- and angular-resolved distributions at the wall, the refined ERO2.0 simulations confirm the earlier findings in [1] that the W source is dominated by Ne sputtering with W self-sputtering the second largest contributor. The W core-plasma influx depends strongly on the SOL fuel ion flow patterns and on the assumptions regarding cross-field transport coefficients imposed in the modelling. To quantify the impact of the latter, simulations with pure anomalous transport are compared against a combination of anomalous and neoclassical transport. Neoclassical transport profiles for cross-field pinch and diffusion are incorporated from FACIT calculations based on local pedestal plasma conditions. In general, highest influxes are observed for W originating from main chamber panels, while the influx from the divertor is low, confirming the strong divertor screening found in previous studies.

[1] R. A. Pitts et al., NME 42, 101854 (2025)
[2] T. Wauters, plenary at this conference

Authors

Christoph Baumann (Forschungszentrum Jülich GmbH) Henri Kumpulainen (FZJ) Juri Romazanov (Forschungszentrum Jülich) Sebastian Rode (Forschungszentrum Jülich GmbH) Andreas Kirschner (Forschungszentrum Jülich GmbH) Sebastijan Brezinsek (Forschungszentrum Jülich) Andrei Pshenov (ITER Organization (IO)) Tom Wauters (ITER Organization (IO)) Richard A. Pitts (ITER Organisation, France) Alberto Loarte (ITER Organization)

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