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Quench Analysis of the DEMO CS1 Coil
Cryogenics ( IF 1.8 ) Pub Date : 2020-12-01 , DOI: 10.1016/j.cryogenics.2020.103194
Aleksandra Dembkowska , Monika Lewandowska , Xabier Sarasola , Kamil Sedlak

Abstract The European DEMOnstration Fusion Power Plant (EU-DEMO) is being designed as an intermediary stage between the ITER experimental reactor and future commercial fusion power plants. The EU-DEMO is based on the tokamak concept with a fully superconducting magnet system. The Central Solenoid (CS) of the EU-DEMO will consist of five modules, namely: CSU3, CSU2, CS1, CSL2 and CSL3, located vertically one above the other. The central CS1 module will be subjected to the most demanding operating conditions (the highest magnetic field and mechanical loads). Two concepts of the CS1 winding pack (WP) are being designed by CEA IRFM (France) and EPFL-SPC (Switzerland) teams. The pancake wound WP proposed by CEA is based on Wind & React Nb3Sn Cable-in-Conduit Conductor, whereas the hybrid WP developed by EPFL-SPC consist of 10 sub-coils, layer-wound using: HTS (RE-123), React & Wind Nb3Sn and NbTi conductors in the high, medium and low field sections, respectively. Each design iteration undergoes comprehensive electromagnetic, mechanical and thermal-hydraulic analyses aimed at verification if it fulfils the design performance criteria. Our present work is focused on the quench analysis of all the hybrid CS1 sub-coils, aimed at the assessment of the maximum hot-spot temperature. The analysis, based on the iteration of the hybrid design proposed in 2017, is performed using the THEA CryoSoft code. We assume that quench is initiated at the beginning of premagnetization phase and include in our model the realistic magnetic field distribution along each conductor computed with 2D axi-symmetrical finite element model in ANSYS. We study the effect of taking into account heat transfer between neighbouring turns and heat generation due to AC losses during the fast discharge on the value of the hot spot temperature.

中文翻译:

DEMO CS1 线圈的淬火分析

摘要 欧洲示范聚变发电厂 (EU-DEMO) 被设计为 ITER 实验反应堆和未来商业聚变发电厂之间的中间阶段。EU-DEMO 基于具有完全超导磁体系统的托卡马克概念。EU-DEMO 的中央电磁阀 (CS) 将由五个模块组成,即:CSU3、CSU2、CS1、CSL2 和 CSL3,它们垂直放置在另一个模块上。中央 CS1 模块将承受最苛刻的操作条件(最高的磁场和机械负载)。CEA IRFM(法国)和 EPFL-SPC(瑞士)团队正在设计 CS1 绕线包 (WP) 的两个概念。CEA 提出的煎饼缠绕 WP 基于 Wind & React Nb3Sn 线管导体,而 EPFL-SPC 开发的混合 WP 由 10 个子线圈组成,层绕:分别在高、中和低场部分使用 HTS (RE-123)、React & Wind Nb3Sn 和 NbTi 导体。每个设计迭代都经过全面的电磁、机械和热工水力分析,旨在验证它是否满足设计性能标准。我们目前的工作重点是对所有混合 CS1 子线圈的淬火分析,旨在评估最大热点温度。该分析基于 2017 年提出的混合设计的迭代,使用 THEA CryoSoft 代码执行。我们假设失超是在预磁化阶段开始时开始的,并且在我们的模型中包含了沿每个导体的实际磁场分布,这些磁场分布是使用 ANSYS 中的二维轴对称有限元模型计算的。
更新日期:2020-12-01
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