Recent Publications

Sep 25

Nuclear Fusion

On the relationship between the H-mode separatrix density and engineering parameters across multiple tokamaks: physics-based models, regression, and extrapolations to next-step devices

Davide Silvagni, Ondřej Grover, Adriano Stagni, Jerry W Hughes, Marco Andrés Miller, Bartosz Lomanowski, L. Balbinot, Guido Ciraolo, Wouter Dekeyser, Michael G Dunne, et al.

The electron density at the separatrix (n e,sep ) plays a central role in balancing energy confinement, detachment achievement, and ELM suppression in tokamaks, thereby influencing core-edge integration. To study what determines this key parameter, a database of H-mode separatrix density measurements from the Alcator C-Mod, ASDEX Upgrade, and JET tokamaks has been assembled using a consistent analysis method across all devices. This dataset is used to assess the validity of a physics-based predictive model and to derive a regression scaling expression for n e,sep , both requiring only engineering parameters as input. The theory-based expression is obtained by coupling two-point model equations with simple geometrical relations, and successfully reproduces experimental measurements across all three devices, with the exception of a common multiplicative constant. The regression confirms similar parameter dependencies, revealing a positive dependence on divertor neutral pressure and the ratio of the power entering the scrape-off layer to the major radius, a negative dependence on the toroidal magnetic field and minor radius, and no significant dependence on the plasma current. Both the resulting scaling and theory-based expressions predict n e,sep within a factor of 1.5 across the three machines, and provide projections to next-step devices (ITER, SPARC, DTT, JT-60SA and COMPASS-U) that are in agreement with available SOLPS simulations.

Sep 15

Plasma Physics and Controlled Fusion

Negative triangularity studies in view of DTT operations

Paola Mantica, Lorenzo Aucone, Alessandro Balestri, Alberto Mariani, Roberto Ambrosino, Justin Ball, A. Castaldo, Stefano Coda, Tim Happel, Joerg Hobirk, et al.

Plasma Physics and Controlled FusionSep 15, 2026Plasma & ConfinementAI, Modeling & Simulation

This paper summarizes experimental and modelling work carried out across the last 5 years on Negative Triangularity (NT) scenarios in view of future DTT operations. The shapes foreseen for DTT have been tested experimentally on TCV and ASDEX Upgrade (AUG). Integrated modelling using ASTRA/TGLF and local gyrokinetic simulations using GENE have been performed on the experimental results and to predict DTT scenarios. Experiments and modelling find a stronger beneficial effect of NT in TCV than in AUG. DTT predictions are more in line with AUG results. Various mechanisms to explain this difference have been examined and are discussed. In all devices, the NT scenarios provide a viable ELM-free alternative to Positive Triangularity ELMy H-modes, with central values of pressure comparable or even higher.

Sep 13

Aug 22

Aug 17

Nuclear Fusion

The status and design challenges of the heating and current drive systems for DTT

Gustavo Granucci, Silvio Ceccuzzi, Afra Romano, Andrea Murari, Gian Luca Ravera, Piero Agostinetti, Sofia Bertolami, Falk Braunmüller, Alessandro Bruschi, Daniele Busi, et al.

This paper reports the main design keys and the challenging issues of the Heating and Current Drive System (HCD) of the Divert Tokamak Test (DTT) facility that is under construction at ENEA site in Frascati with the aim to perform studies on the power exhaust in a flexible and easily modifiable environment. The selected HCD systems for DTT are those with the most consolidated technology and expected to be relevant for the future reactor. The status of each system is reported, both in terms of design and procurement, which are well advanced for the system required in the first phase of the DTT exploitation: electron and ion cyclotron resonant heating. The third system is neutral beam injector, based on negative ion acceleration, which will be installed in DTT in a second phase, after the first five years of operation. The full heating power will be reached with the doubling of the radiofrequency power to reach the 45 MW at plasma needed to test the divertor with a power density at reactor level.

Aug 5

Jul 31

Nuclear Fusion

Orbital frequency spectrum and resonant response of realistic tokamak equilibria

Panagiotis Zestanakis, Yannis Antonenas, Giorgos Anastassiou, Matteo Valerio Falessi, Yannis Kominis

We present a fast geometric method for calculating guiding center (GC) frequencies in numerical axisymmetric tokamak equilibria. This approach provides a cost-effective means of identifying resonant orbits and offers an intuitive explanation of the role of the equilibrium on the Orbital Frequency Spectrum (OFS) and resonance conditions. We apply the method to two equilibria, one from the ASDEX Upgrade (AUG) and one from the Divertor Tokamak Test facility (DTT) and demonstrate its ability to predict the location of resonant islands under perturbations as well as the existence of transport barriers. Both static non-axisymmetric and time-dependent axisymmetric perturbations are considered. Crucially, the method itself lays the groundwork for developing a reduced-order model for ion transport based on resonance analysis of unperturbed GC dynamics.

Jul 26

arXiv (physics.plasm-ph)

Implementation and first application of EMC3-EIRENE on DTT for assessing the heat load on the ICRH antenna

H. S. Wu, Y. Feng, F. Subba, S. Ceccuzzi, P. Innocente, M. M. Robaldo, A. A. Tuccillo, R. Zanino

This paper reports on the implementation process of the three-dimensional (3D) edge plasma transport code EMC3-EIRENE on the Divertor Tokamak Test (DTT) facility and the results of its first application, with a focus on assessing the heat load on the Ion Cyclotron Resonance Heating (ICRH) antenna surfaces. Using axisymmetric geometries and the SOLPS-ITER simulation results as a reference, we first evaluate the performance of the EMC3-EIRENE in describing axisymmetric plasmas to ensure correct code modelling setup for later complex 3D applications. We then incorporate the ICRH antenna structure in our 3D simulations, assuming different toroidal symmetry for the antenna to determine whether the heat load assessment can be carried out with reduced computational effort, and to what extent a 3D assessment deviates from a 2D approximation. The predictions of the 3D antenna heat load distribution are obtained and the peak values on the top plate and the two side plates reach 0.9, 2.1 and 3.8 MW/m2, respectively. Finally, 3D gas puffing is included to evaluate its impact on the antenna heat load. The corresponding 3D edge plasma behavior is presented under the coupled effects of gas puffing and the antenna geometrical structure.

Jul 21

Nuclear Fusion

The Divertor Tokamak Test Facility Research Plan

Gerardo Giruzzi, P Martin, Clemente Angioni, Sebastijan Brezinsek, Flavio Crisanti, Giacomo Dose, Matteo Valerio Falessi, Paolo Innocente, Paola Mantica, Eric Nardon, et al.

The Divertor Tokamak Test facility (DTT) is a device presently under construction at the ENEA site in Frascati (Italy) in the framework of a joint public/private partnership. It has been designed as a superconducting tokamak with breakeven class performance, with the main objective of developing credible solutions for heat and particle exhaust, a key challenge in view of future fusion reactors. This needs to be addressed in a core-edge integrated approach, to assess the compatibility of exhaust solutions with reactor relevant core performance. In this paper, an overview is provided of the DTT research plan, recently developed by an international team. It covers the DTT programmatic objectives, research strategy and expected scientific contributions connected with the device characteristics, not only in the key area of heat exhaust and edge plasma physics, but also on other subjects of high fusion relevance, such as MHD stability in high performance scenarios, transport and turbulence, energetic particle physics, validation of advanced theoretical developments, as well as tests of technological solutions for reactor relevant components.

Jul 8

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