DEMO CS线圈用CORCⓇ导体的热水力分析

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Monika Lewandowska , Aleksandra Dembkowska , Rafał Ortwein , Arend Nijhuis , Giulio Anniballi , Lorenzo Giannini , Danko C. van der Laan , Jeremy Weiss , Gianluca De Marzi , Davide Uglietti
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引用次数: 0

摘要

高温超导体(HTS)被认为是未来高场核聚变磁体的一种很有前途的解决方案。各种HTS电缆概念,如扭曲堆叠电缆、交叉导体(CroCo)、罗贝尔组装涂层导体(RACC)、圆芯导体(CORCⓇ)、HTS导管内电缆导体(CICC)、罗贝尔排列排列的排列堆叠(ASTRA)等已被提出。其中一些已经被考虑用于EU-DEMO磁铁系统的某些组件中。最近提出了一种基于CORCⓇ概念的EU-DEMO混合中央螺线管(CS)线圈最内层导体的设计。在本工作中,我们使用Cryosoft的THEA代码模拟了该导体在电流周期内的正常工作。考虑了CS1几何形状的两种变体:单个CS1模块和分为两个子模块(CS1L和CS1U)的CS1模块,其中一个位于另一个之上。考虑到磁滞和耦合损耗引起的热负荷,以及沿导体磁场分布的时间演变,我们估计了导体内的最低温度裕度,以验证其是否满足性能标准:min(ΔTmarg) >;1.5 K。利用ANSYS机械APDL模型(3D固体+ 1D流体)对导体截面径向温度梯度进行了模拟,并与一维THEA模型的模拟结果进行了补充。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Thermal-hydraulic analysis of the CORCⓇ conductor for the DEMO CS coil
Conductors using High Temperature Superconductor (HTS) tapes are considered as a very promising solution for future high-field fusion magnets. Various HTS cable concepts, such as e.g. twisted stack cable, cross-conductor (CroCo), Roebel assembled coated conductor (RACC), conductor on round core (CORC), HTS cable-in-conduit conductor (CICC), aligned stacks transposed in Roebel arrangement (ASTRA) have been proposed. Some of them are already considered for potential use in some components of the EU-DEMO magnet system. Recently a design of a conductor based on the CORC concept for the innermost layer of the hybrid Central Solenoid (CS) coil of EU-DEMO was proposed. In the present work we simulated, using the THEA code by Cryosoft, normal operation of this conductor during the current cycle. Two variants of the CS1 geometry were considered: a single CS1 module, and a CS1 module split into two sub-modules (CS1L and CS1U) located one above the other. Taking into account heat loads due to the hysteresis and coupling losses, resulting from time evolution of the magnetic field profile along the conductor, we estimated the minimum temperature margin in the conductor, to verify if it fulfills the performance criterion: min(ΔTmarg) > 1.5 K. The results obtained with the 1D THEA model were complemented by the results of simulations with the ANSYS Mechanical APDL model (3D solid + 1D fluid) aimed at the assessment of radial temperature gradients in the conductor cross-section.
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来源期刊
Fusion Engineering and Design
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.
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