液态金属导流器开发的物理与技术研究,重点是锡毛细管多孔系统溶液,在OLMAT高热流密度设施

IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
A. de Castro, E. Oyarzábal, D. Alegre, D. Tafalla, M. González, K. J. McCarthy, J. G. A. Scholte, T. W. Morgan, F. L. Tabarés, the OLMAT team
{"title":"液态金属导流器开发的物理与技术研究,重点是锡毛细管多孔系统溶液,在OLMAT高热流密度设施","authors":"A. de Castro,&nbsp;E. Oyarzábal,&nbsp;D. Alegre,&nbsp;D. Tafalla,&nbsp;M. González,&nbsp;K. J. McCarthy,&nbsp;J. G. A. Scholte,&nbsp;T. W. Morgan,&nbsp;F. L. Tabarés,&nbsp;the OLMAT team","doi":"10.1007/s10894-023-00373-9","DOIUrl":null,"url":null,"abstract":"<div><p>The operation of the Optimization of Liquid Metal Advanced Targets (OLMAT) facility began in April 2021 with the scientific objective of exposing liquid-metal plasma facing components (PFCs) to the particle and power fluxes provided by one of the hydrogen neutral beam injectors of the TJ-II stellarator. The system can deliver heat fluxes from 5 to 58 MW m<sup>−2</sup> of high energy hydrogen neutral particles (≤ 33 keV) with fluxes up to 10<sup>22 </sup>m<sup>2 </sup>s<sup>−1</sup> (containing an ion fraction ≤ 33% in some instances), pulsed operation of 30–150 ms duration and repetition rates up to 2 min<sup>−1</sup>. These characteristics enable OLMAT as a high heat flux (HHF) facility for PFC evaluation in terms of power exhaust capabilities, thermal fatigue and resilience to material damage. Additionally, the facility is equipped with a wide range of diagnostics that includes tools for analyzing the thermal response of the targets as well as for monitoring atomic/plasma physics phenomena. These include spectroscopy, pyrometry, electrical probing and visualization (fast and IR cameras) units. Such particularities make OLMAT a unique installation that can combine pure technological PFC research with the investigation of physical phenomena such as vapor shielding, thermal sputtering, the formation/characterization of plasma plumes with significant content of evaporated metal and the detection of impurities in front of the studied targets. Additionally, a myriad of surface characterization techniques as SEM/EDX for material characterization of the exposed PFC prototypes are available at CIEMAT. In this article, first we provide an overview of the current facility upgrade in which a high-power CW laser, that can be operated in continuous and pulsed modes (0.2–10 ms), dump and electrical (single Langmuir) probe embedded on the target surface have been installed. This laser operation will allow simulating more relevant heat loading scenarios such as nominal steady-state divertor heat fluxes (10–20 MW m<sup>−2</sup> in continuous mode) and transients including ELM loading and disruption-like events (ms time scales and power densities up to GW m<sup>−2</sup> range). The work later focuses on the more recent experimentation (2022 fall campaign) where a 3D printed Tungsten (W) Capillary Porous System (CPS) target, with approximated 30 μm pore size and a 37% porosity and filled with liquid tin. This porous surface was a mock-up of the PFC investigated in the ASDEX Upgrade divertor manipulator. The target composed with this element was eventually exposed to a sequence of shots with the maximum heat flux that OLMAT provides (58 ± 14 MWm<sup>−2</sup>). Key questions as resilience to dry-out and particle ejection of the liquid metal layer, its refilling, the induced damage/modification of the porous W matrix and the global performance of the component are addressed, attempting to shed light on the issues encountered with the PFC at tokamak scale testing.</p></div>","PeriodicalId":634,"journal":{"name":"Journal of Fusion Energy","volume":"42 2","pages":""},"PeriodicalIF":1.9000,"publicationDate":"2023-09-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://link.springer.com/content/pdf/10.1007/s10894-023-00373-9.pdf","citationCount":"0","resultStr":"{\"title\":\"Physics and Technology Research for Liquid-Metal Divertor Development, Focused on a Tin-Capillary Porous System Solution, at the OLMAT High Heat-Flux Facility\",\"authors\":\"A. de Castro,&nbsp;E. Oyarzábal,&nbsp;D. Alegre,&nbsp;D. Tafalla,&nbsp;M. González,&nbsp;K. J. McCarthy,&nbsp;J. G. A. Scholte,&nbsp;T. W. Morgan,&nbsp;F. L. Tabarés,&nbsp;the OLMAT team\",\"doi\":\"10.1007/s10894-023-00373-9\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>The operation of the Optimization of Liquid Metal Advanced Targets (OLMAT) facility began in April 2021 with the scientific objective of exposing liquid-metal plasma facing components (PFCs) to the particle and power fluxes provided by one of the hydrogen neutral beam injectors of the TJ-II stellarator. The system can deliver heat fluxes from 5 to 58 MW m<sup>−2</sup> of high energy hydrogen neutral particles (≤ 33 keV) with fluxes up to 10<sup>22 </sup>m<sup>2 </sup>s<sup>−1</sup> (containing an ion fraction ≤ 33% in some instances), pulsed operation of 30–150 ms duration and repetition rates up to 2 min<sup>−1</sup>. These characteristics enable OLMAT as a high heat flux (HHF) facility for PFC evaluation in terms of power exhaust capabilities, thermal fatigue and resilience to material damage. Additionally, the facility is equipped with a wide range of diagnostics that includes tools for analyzing the thermal response of the targets as well as for monitoring atomic/plasma physics phenomena. These include spectroscopy, pyrometry, electrical probing and visualization (fast and IR cameras) units. Such particularities make OLMAT a unique installation that can combine pure technological PFC research with the investigation of physical phenomena such as vapor shielding, thermal sputtering, the formation/characterization of plasma plumes with significant content of evaporated metal and the detection of impurities in front of the studied targets. Additionally, a myriad of surface characterization techniques as SEM/EDX for material characterization of the exposed PFC prototypes are available at CIEMAT. In this article, first we provide an overview of the current facility upgrade in which a high-power CW laser, that can be operated in continuous and pulsed modes (0.2–10 ms), dump and electrical (single Langmuir) probe embedded on the target surface have been installed. This laser operation will allow simulating more relevant heat loading scenarios such as nominal steady-state divertor heat fluxes (10–20 MW m<sup>−2</sup> in continuous mode) and transients including ELM loading and disruption-like events (ms time scales and power densities up to GW m<sup>−2</sup> range). The work later focuses on the more recent experimentation (2022 fall campaign) where a 3D printed Tungsten (W) Capillary Porous System (CPS) target, with approximated 30 μm pore size and a 37% porosity and filled with liquid tin. This porous surface was a mock-up of the PFC investigated in the ASDEX Upgrade divertor manipulator. The target composed with this element was eventually exposed to a sequence of shots with the maximum heat flux that OLMAT provides (58 ± 14 MWm<sup>−2</sup>). Key questions as resilience to dry-out and particle ejection of the liquid metal layer, its refilling, the induced damage/modification of the porous W matrix and the global performance of the component are addressed, attempting to shed light on the issues encountered with the PFC at tokamak scale testing.</p></div>\",\"PeriodicalId\":634,\"journal\":{\"name\":\"Journal of Fusion Energy\",\"volume\":\"42 2\",\"pages\":\"\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2023-09-04\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"https://link.springer.com/content/pdf/10.1007/s10894-023-00373-9.pdf\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Journal of Fusion Energy\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://link.springer.com/article/10.1007/s10894-023-00373-9\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Fusion Energy","FirstCategoryId":"5","ListUrlMain":"https://link.springer.com/article/10.1007/s10894-023-00373-9","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

摘要

液态金属先进目标优化(OLMAT)设施的运行始于2021年4月,其科学目标是将液态金属等离子体面向组件(pfc)暴露于TJ-II星射器的一个氢中性束注入器提供的粒子和功率通量中。该系统可以提供5至58 MW m - 2的高能氢中性粒子(≤33 keV)的热通量,通量高达1022 m2 s - 1(在某些情况下含有离子分数≤33%),脉冲操作持续时间为30-150 ms,重复率高达2 min - 1。这些特性使OLMAT成为一种高热流密度(HHF)设备,用于PFC在功率排气能力、热疲劳和材料损伤恢复方面的评估。此外,该设施还配备了广泛的诊断工具,包括分析目标的热响应以及监测原子/等离子体物理现象的工具。这些包括光谱学、高温测量、电探测和可视化(快速和红外相机)装置。这些特性使OLMAT成为一个独特的装置,它可以将纯技术PFC研究与物理现象的研究相结合,如蒸汽屏蔽、热溅射、具有大量蒸发金属的等离子体羽流的形成/表征以及在研究目标前面检测杂质。此外,CIEMAT还提供了大量的表面表征技术,如用于暴露的PFC原型材料表征的SEM/EDX。在本文中,我们首先概述了目前的设备升级,其中安装了高功率连续波激光器,可以在连续和脉冲模式(0.2-10 ms)下工作,转储和嵌入目标表面的电(单Langmuir)探头。这种激光操作将允许模拟更相关的热负载场景,例如标称稳态分流器热通量(连续模式下10-20 MW m - 2)和瞬态,包括ELM加载和类似中断的事件(ms时间尺度和功率密度高达GW m - 2范围)。随后的工作重点是最近的实验(2022年秋季),其中3D打印钨(W)毛细多孔系统(CPS)目标,孔径约为30 μm,孔隙率为37%,并填充液态锡。该多孔表面是ASDEX升级导流器操作器中PFC的模型。由该元件组成的目标最终暴露于OLMAT提供的最大热通量(58±14 MWm−2)的一系列射击中。关键问题,如弹性干和颗粒喷射的液态金属层,它的再填充,诱导损伤/修改多孔W基体和组件的整体性能被解决,试图阐明PFC在托卡马克规模测试中遇到的问题。
本文章由计算机程序翻译,如有差异,请以英文原文为准。

Physics and Technology Research for Liquid-Metal Divertor Development, Focused on a Tin-Capillary Porous System Solution, at the OLMAT High Heat-Flux Facility

Physics and Technology Research for Liquid-Metal Divertor Development, Focused on a Tin-Capillary Porous System Solution, at the OLMAT High Heat-Flux Facility

The operation of the Optimization of Liquid Metal Advanced Targets (OLMAT) facility began in April 2021 with the scientific objective of exposing liquid-metal plasma facing components (PFCs) to the particle and power fluxes provided by one of the hydrogen neutral beam injectors of the TJ-II stellarator. The system can deliver heat fluxes from 5 to 58 MW m−2 of high energy hydrogen neutral particles (≤ 33 keV) with fluxes up to 1022 m2 s−1 (containing an ion fraction ≤ 33% in some instances), pulsed operation of 30–150 ms duration and repetition rates up to 2 min−1. These characteristics enable OLMAT as a high heat flux (HHF) facility for PFC evaluation in terms of power exhaust capabilities, thermal fatigue and resilience to material damage. Additionally, the facility is equipped with a wide range of diagnostics that includes tools for analyzing the thermal response of the targets as well as for monitoring atomic/plasma physics phenomena. These include spectroscopy, pyrometry, electrical probing and visualization (fast and IR cameras) units. Such particularities make OLMAT a unique installation that can combine pure technological PFC research with the investigation of physical phenomena such as vapor shielding, thermal sputtering, the formation/characterization of plasma plumes with significant content of evaporated metal and the detection of impurities in front of the studied targets. Additionally, a myriad of surface characterization techniques as SEM/EDX for material characterization of the exposed PFC prototypes are available at CIEMAT. In this article, first we provide an overview of the current facility upgrade in which a high-power CW laser, that can be operated in continuous and pulsed modes (0.2–10 ms), dump and electrical (single Langmuir) probe embedded on the target surface have been installed. This laser operation will allow simulating more relevant heat loading scenarios such as nominal steady-state divertor heat fluxes (10–20 MW m−2 in continuous mode) and transients including ELM loading and disruption-like events (ms time scales and power densities up to GW m−2 range). The work later focuses on the more recent experimentation (2022 fall campaign) where a 3D printed Tungsten (W) Capillary Porous System (CPS) target, with approximated 30 μm pore size and a 37% porosity and filled with liquid tin. This porous surface was a mock-up of the PFC investigated in the ASDEX Upgrade divertor manipulator. The target composed with this element was eventually exposed to a sequence of shots with the maximum heat flux that OLMAT provides (58 ± 14 MWm−2). Key questions as resilience to dry-out and particle ejection of the liquid metal layer, its refilling, the induced damage/modification of the porous W matrix and the global performance of the component are addressed, attempting to shed light on the issues encountered with the PFC at tokamak scale testing.

求助全文
通过发布文献求助,成功后即可免费获取论文全文。 去求助
来源期刊
Journal of Fusion Energy
Journal of Fusion Energy 工程技术-核科学技术
CiteScore
2.20
自引率
0.00%
发文量
24
审稿时长
2.3 months
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.
×
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
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
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 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术官方微信