Design and analysis of cooling water system for ECRH and ICRF testing bench

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-07-16 DOI:10.1016/j.fusengdes.2024.114572
{"title":"Design and analysis of cooling water system for ECRH and ICRF testing bench","authors":"","doi":"10.1016/j.fusengdes.2024.114572","DOIUrl":null,"url":null,"abstract":"<div><p>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.</p></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-07-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379624004241","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

Abstract

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.

查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
为 ECRH 和 ICRF 试验台设计和分析冷却水系统
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。
求助全文
约1分钟内获得全文 去求助
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.
期刊最新文献
On the fabrication of ultrafine-grained potassium-doped tungsten: Mechanical milling and spark plasma sintering of K-doped W powder prepared by evaporation-condensation method X-ray imaging crystal spectrometer (XICS) diagnostic on the HL-3 tokamak The energy output equilibrium scheme with intermediate energy storage for tokamak fusion power plant Measurement of the mechanical vibration and its impact on the magnetic diagnostics in the J-TEXT tokamak Overview of the TCV digital real-time plasma control system and its applications
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术
文献互助 智能选刊 最新文献 互助须知 联系我们:info@booksci.cn
Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。
Copyright © 2023 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1