Thermal-hydraulic analysis of the cool-down for the CFETR TF coil using the 4C code

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

Fusion Engineering and Design Pub Date : 2025-04-14 DOI:10.1016/j.fusengdes.2025.114988

Xinghao Wen , Roberto Bonifetto , Junjun Li , Roberto Zanino , Yu Wu

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引用次数: 0

Abstract

The China Fusion Engineering Test Reactor (CFETR) will be a superconducting tokamak featuring sixteen toroidal field (TF) coils; a full-size TF coil, based on a national scientific research project, has been designed and is currently being built. The first cool-down test of the TF coil is foreseen to take place in 2025. During the entire cool-down process, it is necessary to ensure that the temperature difference between any two positions of the TF coil is <50 K to avoid irreversible damage to the coil caused by excessive thermal stress. However, the maximum temperature (T_max) within the TF coil cannot be directly and accurately obtained through experimental measurements; therefore, the thermal hydraulic analysis is crucial to prepare the cool-down strategy of the coil. In this paper, the first cool-down analysis of one CFETR TF coil is completed using the 4C code. The code is based on a 1D model of the helium flow inside the cable-in-conduit conductors coupled to a set of 2D cross sections of the steel structures, where the heat conduction is modeled. The thermal coupling between the turns and the pancakes, as well as the coupling between winding and casing, is also considered. The maximum temperature evolution within the magnet is computed and the optimized cool-down strategy (inlet temperature, inlet and outlet pressure evolution) is proposed.

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使用 4C 代码对 CFETR TF 线圈的冷却进行热液压分析

中国聚变工程试验堆（CFETR）将是一个超导托卡马克，具有16个环形场（TF）线圈；基于国家科研项目，已设计并正在建设全尺寸TF线圈。TF线圈的第一次冷却试验预计将在2025年进行。在整个冷却过程中，必须保证TF线圈任意两个位置之间的温差为50 K，以避免过高的热应力对线圈造成不可逆的损坏。然而，TF线圈内部的最高温度（Tmax）无法通过实验测量直接准确地获得；因此，热水力分析对于制定盘管冷却策略至关重要。本文利用4C代码对某CFETR TF线圈进行了首次冷却分析。该代码基于管道内电缆导体内部氦流的一维模型，该模型与钢结构的一组二维截面相耦合，其中热传导是建模的。文中还考虑了弯道与薄层之间的热耦合以及绕组与机匣之间的热耦合。计算了磁体内部的最大温度演变，并提出了优化冷却策略（进口温度、进出口压力演变）。

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.