CNR ExploRA

Articolo in rivista, 2023, ENG, 10.1088/1361-6587/acc2e3

Divertor power spreading in the Divertor Tokamak Test facility for a full power scenario with Ar and Ne seeding

Ivanova-Stanik I.; Chmielewski P.; Day C.; Innocente P.; Zagorski R.

Institute of Plasma Physics and Laser Microfusion, Warsaw, Poland; Karlsruhe Institute of Technology (KIT), Institute for Technical Physics, Karlsruhe, Germany; Consorzio RFX (CNR, ENEA, INFN, Università di Padova, Acciaierie Venete SpA), Padova and CNR ISTP - Istituto per la Scienza e Tecnologia dei Plasmi, Sede di Padova, Italy; National Centre for Nuclear Research (NCBJ), Otwock, Poland.

This work describes integrated numerical modelling applied to Divertor Tokamak Test (DTT) scenarios with tungsten wall and divertor in single null configuration using the COREDIV code, which self-consistently solves 1D radial transport equations of plasma and impurities in the core region and 2D multi-fluid transport in the scrape-off layer (SOL). COREDIV code simulations have been performed and compared to the already published solutions from JETTO for DTT full power discharges with Ar seeding. The influence of the particle transport on the fuelling and flux to the plate is analysed. The main conclusion from the performed simulations is that Ne and Ar radiate effectively in the SOL and no difference was found in the fuelling properties between them. The fuelling increases with increase in radial transport in the core region. It has been found that the rise in the diffusion in the core plasma has a small influence on several global plasma parameters, such as plasma radiation, impurity concentration and fluxes to the divertor plate, but has a strong effect on the fuelling. The fuelling and deuterium flux to the plate decrease almost linearly with decreasing plasma density, keeping ? n e ? / n e s e p = constant.

Plasma physics and controlled fusion (Print) 65 (5), pp. 055009-1–055009-10