Description
The Divertor Tokamak Test (DTT) facility, which is currently under construction in Frascati, will be dedicated to developing credible solutions for heat and particle exhaust. The facility assesses the compatibility of exhaust solutions with reactor-relevant core performance in a core-edge integrated approach. Its design phase has been supported by intensive scenario modelling, facilitating the optimization of auxiliary heating, informing diagnostic development, and providing inputs for MHD stability analysis, neutron‑yield estimates, fast‑particle loss studies and fueling strategies [1]. Utilizing the JINTRAC code and the ASTRA code, the modelling covers all phases of the plasma discharges: current ramp-up, flat-top and ramp-down, using state-of-art physics-based transport models, i.e., TGLF-SAT2, NCLASS and FACIT for predictions of temperatures, density, impurity species and current density [2,3]. Starting from the early scenario A with only 7.2 MW of ECH power and no ICRH or NBI, up to the scenario E with full power of 45 MW, this contribution presents the scenarios achievable and discusses the issues of transport physics that can be addressed in each phase of operation. Negative triangularity (NT) operations have been shown to be a possible option to avoid ELMs and still maintain good performance, in addition to strongly shaped and impurity-seeded positive triangularity scenarios [4]. Advanced Tokamak scenarios achieving high beta with internal transport barriers will be studied at half field (3T) and different power levels [5], providing complementary results to JT-60SA research. For the full power operation phase, we also explored a Hybrid scenario with q95~4 to avoid the large sawteeth present in the q95~3 E baseline scenarios [6]. A structured IMAS-based scenario database has been tested on the ITER SDCC cluster using the SimDB tool. Such a database will support future DTT scenario development, experimental planning and physics study.
References
[1] Crisanti F, et al., 2024 Divertor Tokamak Test Facility Research Plan, Version 1.0, https://www.dtt-project.it/index.php/about/dttresearch-plan.html
[2] Casiraghi I, et al., 2023 Core integrated simulations for the Divertor Tokamak Test facility scenarios towards consistent core-pedestal-SOL modelling Plasma Phys. Control. Fusion 65 035017
[3] Bonanomi N, et al., 2025 Time-dependent full-radius integrated modeling of the DTT tokamak main plasma scenarios Nucl. Fusion 65 016005
[4] Mariani A, et al., 2024 First-principle based predictions of the effects of negative triangularity on DTT scenarios, Nucl. Fusion 64 046018
[5] Auriemma F, et al., 2026 This conference
[6] Lombardo J, et al., 2025 DTT hybrid scenario development with ASTRA-TGLF predictive modelling 51st EPS Conference on Plasma Physics (European Physical Society)