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

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-09-09 DOI:10.1016/j.fusengdes.2025.115416

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

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引用次数: 0

Abstract

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: R₀ = 0.3 m, A = 2.5, I_pla = 0.110 MA, B_t = 0.8 T, q₉₅ = 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.

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大学级托卡马克信托概述：等离子体场景和中断研究的初步表征

托卡马克（Tuscia Research University Small Tokamak）是一个新的大学规模的托卡马克，目前正在Tuscia大学（UNITUS）设计中。本文概述了TRUST的概念设计，以实现目标单零等离子体配置的第一阶段操作，主要参数如下：R0 = 0.3 m, a = 2.5, Ipla = 0.110 MA, Bt = 0.8 T, q95 = 3.2。根据EU-DEMO和DTT提案的科学计划，该实验的主要目标之一是实现灵活且低成本的大学级实验，以培养下一代聚变工程师和物理学家，为长期研究电力排放问题做好准备。该系统的设计允许轻松更换面向等离子体的组件，并测试创新技术（即超材料），包括使用工作在77 K的高温超导体（HTS）对极向场线圈进行可行的升级。此外，将解释TRUST替代磁布局（AML）概念设计，包括组装/拆卸阶段的建议解决方案。预计未来TRUST操作的三种不同的等离子体配置：单空（SN）、双空（DN）和上单空（USN）。详细分析了每个等离子体场景，特别关注在特征脉冲相位优化有源线圈电流，以实现理想的磁场配置和合适的等离子体参数。通过EM情景分析，初步估计了第一壁和转向器的热负荷和等离子体温度，并对TRUST垂直稳定性进行了初步分析。此外，提出了一个初步的等离子体破坏数据库，其中包括涵盖操作空间内各种等离子体动态条件的电磁数值模拟集合。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.