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

Tungsten dust ingress in WEST: an integrated modelling approach

Not scheduled
20m
EICC, Edinburgh

EICC, Edinburgh

150 Morrison St, Edinburgh EH3 8EE
Oral Presentation Other - MCF

Description

Tokamak operation with tungsten walls, as foreseen in ITER and future fusion-based power plants, faces the potential strong impact of tunsgten dust ingress in the plasma. This was documented on the WEST tokamak [Bucalossi2024], equipped with an ITER-grade tungsten divertor, during a high fluence campaign in attached divertor condition: the erosion of tungsten monoblocks generated deposits that could detach and trigger plasma disruptions [Gaspar2024]. The operation in a radiative divertor regime mitigates the risk of building tungsten deposits [Gaspar2026], but a deterioration of plasma operation could be seen after cumulating the equivalent of a single ITER pulse (Q=10, 400s) in attached divertor condition. Being able to predict the impact of such dusts in present tokamaks is therefore instrumental, although the task is on many aspects extremely complex [Smirnov2020]. The modelling of tungsten dust penetration in WEST is performed with the DUSTTRACK code [Gervasini2027], investigating the tungsten deposition dependence on the dust size and speed. It shows that for similar range of size and speed, the dust is penetrating further inside in WEST compared to JET [Lazzaro2022], due to the lower plasma temperature. The impact on the plasma evolution is then modelled with the High Fidelity Pulse Simulator (HFPS) based on JINTRAC [Romanelli2024], with different levels of complexity, from a prediction of current diffusion only, up to a prediction of particle (D, N and W) and heat transport using TGLF [Staebler2021]. With current diffusion only, resistive MHD mode triggering on q=2/1 is found for a dust mass above 20µg, consistent with experimental observations [Maget2024]. With the more complete simulation scheme, we find that the localization of the tungsten source inside the plasma boundary plays an essential role in the observed plasma evolution. The validation of this workflow on WEST is a first step towards the evaluation of the maximum allowed dust size in larger tokamaks and the associated mitigation strategies.

[Bucalossi2024] Bucalossi J et al, Nuclear Fusion 64, 112022, 2024
[Gaspar2024] Gaspar J et al, Nuclear Materials and Energy 41, 101745, 2024
[Gaspar2026] Gaspar J et al, Plasma Surface Interaction Conference, 2026
[Smirnov2020] Smirnov R et al, Phys. Plasmas 27, 082509, 2020
[Gervasini2027] Gervasini G et al, J Fusion Energy 36, 25, 2017
[Lazzaro2022] Lazzaro E et al, Nucl. Fusion 62, 126037, 2022
[Romanelli2024] Romanelli M et al, Plasma and Fusion Research 9, 3403023, 2014
[Staebler2021] Staebler G et al, Nuclear Fusion 61, 116007, 2021
[Maget2024] Maget P et al, Plasma Phys. Control. Fusion 67, 045005, 2025

Authors

Patrick MAGET (CEA) Dr Gabriele Gervasini (Institute for Plasma Science and Technology, CNR, 20125 Milano, Italy) Dr Enzo Lazzaro (Institute for Plasma Science and Technology, CNR, 20125 Milano, Italy) Francis Casson (CCFE, Culham Science Centre, Abingdon OX14 3DB, United Kingdom of Great Britain and Northern Ireland) Dr Federica Causa (Institute for Plasma Science and Technology, CNR, 20125 Milano, Italy) Dr Pascal Devynck (CEA, IRFM, F-13108 Saint Paul-lez-Durance, France) Nicolas Fedorczak (CEA, IRFM, F-13108 Saint Paul-lez-Durance, France) Dr Jonathan Gaspar (Aix Marseille Univ, CNRS, IUSTI, Marseille, France) Dr James Gunn (CEA, IRFM, F-13108 Saint Paul-lez-Durance, France) Alexis Huart (CEA, IRFM, F-13108 Saint Paul-lez-Durance, France) Florian Koechl (ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 Saint Paul-lezDurance Cedex, France) Pierre Manas (CEA, IRFM, F-13108 Saint Paul-lez-Durance, France) Dr Nicolas Rivals (CEA, IRFM, F-13108 Saint Paul-lez-Durance, France)

Presentation materials

There are no materials yet.