Description
Stability analysis is essential for the reliable operation of magnetic confinement fusion devices, as it prevents degraded confinement, performance loss, and potential damage to plasma-facing components. In this context, detailed stability studies are being performed for the Divertor Tokamak Test (DTT) [1], a device under construction in Frascati, Italy, aimed at testing advanced divertor solutions capable of handling high heat fluxes and power exhaust.This work investigates the DTT full-power scenario using simulations by the JINTRAC transport framework as described in [2]. High-resolution equilibria are computed with the CHEASE code [3] and analyzed using the linear MHD stability code MARS [4]. The scenario features a q<1 region, which can trigger ideal and resistive internal kink modes [5]. Moreover, high-performance regimes relevant to reactor-grade plasmas may destabilize infernal modes, typically localized near rational surfaces characterized by low magnetic shear and steep pressure gradients. Global Alfvénic stability is also assessed as a preliminary step toward including energetic particle effects. Energetic particles generated by auxiliary heating systems, such as radiofrequency heating and neutral beam injection, have velocities comparable to the Alfvén speed and can resonantly excite Alfvén eigenmodes. Their interaction with these modes may degrade fast-ion confinement, hinder core thermalization, compromise burning plasma conditions, and increase wall loads.In this study, energetic particles are produced by a negative neutral beam injection (NNBI) system. Their distribution function, obtained from ASCOT simulations [6,7], is modeled through an anisotropic slowing-down distribution within the hybrid MHD–gyrokinetic framework HYMAGYC [8,9]. This integrated approach enables a comprehensive assessment of both fluid and kinetic properties of the DTT full-power scenario.
[1] R.Martone et al., 2019, DTT Project.
[2] I.Casiraghi et al., Plasma Phys. Control. Fusion 65 (2023) 035017.
[3] H.Lütjens et al., Comput. Phys. Commun. 97 (1996) 219–260.
[4] A.Bondeson et al., Phys. Fluids B 4 (1992) 1889–1900.
[5] V.Fusco et al., EPS 2022, P2a.125.
[6] P.Vincenzi et al., Fus. Eng. Design 189 (2023) 113436
[7] C.De Piccoli et al., Front. Phys. 12 (2024) 1492095.
[8] G.Fogaccia et al., Nucl. Fus., 56:112004, 2016.
[9] G.Vlad et al., Rev. Mod. Plasma Phys. (2025)