Overview of university-class Tokamak TRUST: Preliminary characterization of plasma scenario and disruption studies

• TRUST employs a compact Alternative Magnetic Layout (AML) that repositions the central solenoid around the TF central column, yielding a highly integrated, small-footprint tokamak configuration. • TRUST features an openable equatorial-flange vacuum vessel with demountable TF/PF supports, enabling rapid access and replacement of in-vessel components and coils for experimental campaigns. • Baseline Single-Null plasma scenario for TRUST is defined; Double-Null and Upper Single-Null options have been modeled with optimized coil currents and initial vertical/thermal stability evaluations. • TRUST follows a staged copper-first → HTS-upgrade roadmap; cryostat-ready design provisions and a dedicated HTS development lab support workforce training and de-risk future superconducting coil deployment. • A preliminary electromagnetic/disruption load database for TRUST is guiding structural design decisions for the vacuum vessel, support structures, and in-vessel components. TRUST (Tuscia Research University Small Tokamak) is a new University-scale tokamak currently under design at the University of Tuscia (UNITUS). This paper gives an overview of the TRUST conceptual design, for a first stage of operation to achieve the target single null plasma configuration with the following main parameters: R 0 = 0.3 m, A = 2.5, I pla = 0.110 MA, B t = 0.8 T, q 95 = 3.2. One of the main aims of this experiment is to realise a flexible and low-cost university-class experiment, to train the next generation of fusion engineers and physicists ready to study the power exhaust issues on a long-time scale, according to the scientific program of EU-DEMO and DTT proposals. The system is designed to allow easy replacement of the plasma facing components and testing innovative technologies (i.e., meta-materials) including a feasible upgrade of the poloidal field coils with high temperature superconductors (HTS) working at 77 K. Moreover, TRUST Alternative Magnetic Layout (AML) conceptual design will be explained including the proposed solution for the assembly/disassembly phases. Three distinct plasma configurations for future TRUST operations are foreseen: Single Null (SN), Double Null (DN), and Upper Single Null (USN). Detailed analyses are presented for each plasma scenario, with a particular focus on optimizing active coil currents during characteristic pulse phases to achieve the desired magnetic field configuration with suitable plasma parameters. A preliminary estimation of the thermal loads and plasma temperatures at the first wall and divertor has been made from EM scenario analysis, together with a first analysis on TRUST vertical stability. Additionally, a preliminary plasma disruption database is presented, comprising a collection of EM numerical simulations covering various plasma dynamic conditions within the operational space.

Authors

Institutions

Publication Details

Journal
Fusion Engineering and Design
Published
2025-09-10
DOI
https://doi.org/10.1016/j.fusengdes.2025.115416
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
0.00
Controls
|||
ALL TIME
JAN
FEB
MAR
APR
MAY
JUN
JUL
AUG
SEP
OCT
article

Overview of university-class Tokamak TRUST: Preliminary characterization of plasma scenario and disruption studies

G. Calabrò, R. Lombroni, F. Crisanti, L. Balbinot et al.
Fusion Engineering and Design
Magnetic confinement fusion research
article

Overview of university-class Tokamak TRUST: Preliminary characterization of plasma scenario and disruption studies

G. Calabrò, R. Lombroni, F. Crisanti, L. Balbinot, Pierluigi Fanelli, M. Scarpari, S. Carusotti, M. Notazio
article en

Abstract

• TRUST employs a compact Alternative Magnetic Layout (AML) that repositions the central solenoid around the TF central column, yielding a highly integrated, small-footprint tokamak configuration. • TRUST features an openable equatorial-flange vacuum vessel with demountable TF/PF supports, enabling rapid access and replacement of in-vessel components and coils for experimental campaigns. • Baseline Single-Null plasma scenario for TRUST is defined; Double-Null and Upper Single-Null options have been modeled with optimized coil currents and initial vertical/thermal stability evaluations. • TRUST follows a staged copper-first → HTS-upgrade roadmap; cryostat-ready design provisions and a dedicated HTS development lab support workforce training and de-risk future superconducting coil deployment. • A preliminary electromagnetic/disruption load database for TRUST is guiding structural design decisions for the vacuum vessel, support structures, and in-vessel components. TRUST (Tuscia Research University Small Tokamak) is a new University-scale tokamak currently under design at the University of Tuscia (UNITUS). This paper gives an overview of the TRUST conceptual design, for a first stage of operation to achieve the target single null plasma configuration with the following main parameters: R 0 = 0.3 m, A = 2.5, I pla = 0.110 MA, B t = 0.8 T, q 95 = 3.2. One of the main aims of this experiment is to realise a flexible and low-cost university-class experiment, to train the next generation of fusion engineers and physicists ready to study the power exhaust issues on a long-time scale, according to the scientific program of EU-DEMO and DTT proposals. The system is designed to allow easy replacement of the plasma facing components and testing innovative technologies (i.e., meta-materials) including a feasible upgrade of the poloidal field coils with high temperature superconductors (HTS) working at 77 K. Moreover, TRUST Alternative Magnetic Layout (AML) conceptual design will be explained including the proposed solution for the assembly/disassembly phases. Three distinct plasma configurations for future TRUST operations are foreseen: Single Null (SN), Double Null (DN), and Upper Single Null (USN). Detailed analyses are presented for each plasma scenario, with a particular focus on optimizing active coil currents during characteristic pulse phases to achieve the desired magnetic field configuration with suitable plasma parameters. A preliminary estimation of the thermal loads and plasma temperatures at the first wall and divertor has been made from EM scenario analysis, together with a first analysis on TRUST vertical stability. Additionally, a preliminary plasma disruption database is presented, comprising a collection of EM numerical simulations covering various plasma dynamic conditions within the operational space.

Fusion Engineering and DesignVol. 222
Università degli Studi della Tuscia (IT)
Openalex Percentile: Top 90%
Magnetic confinement fusion research
AI Navigator

Ask Laika to Summarize, Analyze, and Connect papers live on the map.

Summarize Papers & Methodologies

Extract key findings, datasets, and comparative methods across publications.

Benchmark Rankings & Visual Analytics

Rank top research institutions, authors, funders, topics, and journals by Field-Weighted Citation Impact (FWCI) and paper volume with instant charts.

Connect Distant Disciplines

Bridge topological clusters on the map to find hidden collaborative intersections.