{"title":"Preliminary Design of Water-Cooling System for Liquid Metal Divertor Target Test Module in EAST","authors":"Siyao Wang, Zhe Sun, Xinyuan Qian, Xuebing Peng","doi":"10.1007/s10894-024-00412-z","DOIUrl":null,"url":null,"abstract":"<div><p>Developing a robust, feasible, and reliable plasma-facing components (PFCs) is a key mission to realize the commercial fusion power reactor. The situation of the divertor targets will be particularly severe because of higher heat and particle flux in the future devices. In order to improve the power handling capacity and lifetime of the divertor target, a solution of covering the plasma-facing surface of the target with liquid metal was proposed owing to the ability of self-healing. However, liquid metal targets are still in early stages of development and there are many issues need to be explored, especially in the context of the plasma environment in a tokamak. Experimental Advanced Superconducting Tokamak (EAST), aiming to investigate scientific and engineering issues for fusion, provides a suitable environment to study the performance of liquid metal divertor. In this paper, the design of a water-cooling system for liquid metal divertor target test module in EAST is presented. It contains four circulation loops to deal with different accidents to ensure enough safety margin while minimizing the impact on the plasma discharge experiment. The corresponding system safety analyses have been performed and verified that the water-cooling system can meet the design requirements for the liquid metal target test under both normal condition and accidental events. Furthermore, the design of the water-cooling system is compatible with the constraints adopted for the high heat flux components, enhancing its potential for serving other test modules with similar water-cooling requirements in EAST.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"43 1","pages":""},"PeriodicalIF":1.9000,"publicationDate":"2024-05-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Fusion Energy","FirstCategoryId":"5","ListUrlMain":"https://link.springer.com/article/10.1007/s10894-024-00412-z","RegionNum":4,"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
Developing a robust, feasible, and reliable plasma-facing components (PFCs) is a key mission to realize the commercial fusion power reactor. The situation of the divertor targets will be particularly severe because of higher heat and particle flux in the future devices. In order to improve the power handling capacity and lifetime of the divertor target, a solution of covering the plasma-facing surface of the target with liquid metal was proposed owing to the ability of self-healing. However, liquid metal targets are still in early stages of development and there are many issues need to be explored, especially in the context of the plasma environment in a tokamak. Experimental Advanced Superconducting Tokamak (EAST), aiming to investigate scientific and engineering issues for fusion, provides a suitable environment to study the performance of liquid metal divertor. In this paper, the design of a water-cooling system for liquid metal divertor target test module in EAST is presented. It contains four circulation loops to deal with different accidents to ensure enough safety margin while minimizing the impact on the plasma discharge experiment. The corresponding system safety analyses have been performed and verified that the water-cooling system can meet the design requirements for the liquid metal target test under both normal condition and accidental events. Furthermore, the design of the water-cooling system is compatible with the constraints adopted for the high heat flux components, enhancing its potential for serving other test modules with similar water-cooling requirements in EAST.
开发坚固、可行和可靠的面向等离子体的部件(PFCs)是实现商业聚变动力反应堆的关键任务。由于未来装置中的热量和粒子通量更高,分流靶的情况将尤为严峻。为了提高岔流靶的功率处理能力和使用寿命,有人提出了用液态金属覆盖靶面向等离子体表面的解决方案,因为液态金属具有自修复能力。然而,液态金属靶仍处于早期开发阶段,还有许多问题需要探索,特别是在托卡马克中的等离子体环境下。实验性先进超导托卡马克(EAST)旨在研究核聚变的科学和工程问题,为研究液态金属分流器的性能提供了一个合适的环境。本文介绍了 EAST 中液态金属分流器目标测试模块的水冷系统设计。该系统包含四个循环回路,以应对不同的事故,从而确保足够的安全裕度,同时将对等离子体放电实验的影响降至最低。进行了相应的系统安全分析,验证了水冷系统在正常情况和意外事件下都能满足液态金属靶测试的设计要求。此外,水冷系统的设计与高热通量组件所采用的限制条件兼容,增强了其为 EAST 中具有类似水冷要求的其他试验模块提供服务的潜力。
期刊介绍:
The Journal of Fusion Energy features original research contributions and review papers examining and the development and enhancing the knowledge base of thermonuclear fusion as a potential power source. It is designed to serve as a journal of record for the publication of original research results in fundamental and applied physics, applied science and technological development. The journal publishes qualified papers based on peer reviews.
This journal also provides a forum for discussing broader policies and strategies that have played, and will continue to play, a crucial role in fusion programs. In keeping with this theme, readers will find articles covering an array of important matters concerning strategy and program direction.