Multiphysical modelling of superconducting coil discharge through varistors

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-04-10 DOI:10.1016/j.fusengdes.2025.115048

T. Galvin , A. Lampasi , R. Bonifetto , M. De Bastiani

引用次数: 0

Abstract

High-energy silicon-carbide (SiC) varistors will be used as quench protection and energy extraction for the toroidal field (TF) coils of the Divertor Tokamak Test (DTT) facility, as well as the Frascati Coil Cold Test Facility (FCCTF). As varistors have a nonlinear voltage/current response, which is also temperature dependent, multiphysical modelling is required to determine the maximum coil hot-spot temperature during a quench. This paper presents both electrical and thermal-hydraulic modelling of a coil discharge through the varistors, compared to an equivalent linear resistor array. For a single Toroidal Field Coil (TFC), tested in the FCCTF, the varistors discharge the current approximately 10 s faster than linear resistors, resulting in a reduction of the maximum coil hot-spot temperature of 10 K. In DTT with 18 TF coils and 3 discharge assemblies, varistors reduce the discharge time and maximum coil hot-spot temperature by approximately 20 s and 25 K, respectively.

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超导线圈通过压敏电阻放电的多物理模型

高能碳化硅（SiC）压敏电阻将用于托卡马克转向装置（DTT）和弗拉斯卡蒂线圈冷试验装置（FCCTF）的环形场（TF）线圈的淬火保护和能量提取。由于压敏电阻具有非线性的电压/电流响应，这也依赖于温度，因此需要多物理模型来确定淬火期间线圈的最大热点温度。本文介绍了通过压敏电阻的线圈放电的电学和热工模型，并与等效线性电阻阵列进行了比较。对于单个环形场线圈（TFC），在FCCTF中测试，压敏电阻放电电流比线性电阻快约10秒，导致线圈最大热点温度降低10 K。在具有18个TF线圈和3个放电组件的DTT中，压敏电阻分别将放电时间和最大线圈热点温度分别减少了约20秒和25 K。

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.