为 ECRH 和 ICRF 试验台设计和分析冷却水系统

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Lewen Chen , Lei Yang , Weibao Li , Bin Guo , Lili Zhu
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引用次数: 0

摘要

在 EAST(先进超导实验托卡马克)中,ECRH(电子回旋共振加热)和 ICRF(离子回旋频率范围加热)产生的热量应分别通过独立的冷却水系统带走。它们的容量通常是根据 ECRH 和 ICRF 的全功率提出的。事实上,波浪系统的运行时间是有限的,这就需要更大的冷却水冗余容量,占用大量空间,并需要大量预算。本文根据 CRAFT(聚变技术综合研究设施)试验台的要求,设计了 ECRH 和 ICRF 的冷却水系统。之后,利用 AFT Fathom 代码对整个过程进行仿真。最后,设计出了有别于传统的多数一对一模式的多用户集成冷却水系统。冷却水整体结构将为聚变堆冷却水系统的设计提供新的思路。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Design and analysis of cooling water system for ECRH and ICRF testing bench

In EAST(Experimental Advanced Superconducting Tokamak), the heat produced by ECRH (Electron Cyclotron Resonance Heating) and ICRF (Ion Cyclotron range of Frequencies Heating) should be respectively removed through independent cooling water system. Their capacities are typically proposed based on the full power of the ECRH and ICRF. Indeed, the operational duration of the wave system is limited, which necessitates a larger cooling water capacity redundancy, occupies a significant amount of space, and requires a substantial budget. In this paper, the cooling water system for ECRH and ICRF of CRAFT (Comprehensive Research Facility for Fusion Technology) testing bench is designed according to its requirements.Initially, the optimization of the cooling water process is carried out in accordance with the specified parameters. Thereafter, the entire process is simulated employing the AFT Fathom code.Finally, a multiuser integrated cooling water system is designed, which is different from the traditional majority one-to-one mode. And the results show that all the parameters can meet the system requirements, meanwhile the redundancy of the cooling water capacity can be greatly reduced by flow regulation.The cooling water integral structure will provide a new idea for the design of fusion reactor cooling water systems.

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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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