OLMAT高热流密度装置中液锡毛细管多孔系统的热研究

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
M. Reji , E. Oyarzábal , A. de Castro
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引用次数: 0

摘要

聚变装置导流瓦处的极端热和粒子通量是实现可持续聚变能源的最关键挑战之一。固体等离子体表面组件(pfc)通常会受到开裂、侵蚀和熔化的影响,特别是在瞬态事件中,这限制了它们的耐久性和有效性。相比之下,液态金属全氟化合物可能比固态全氟化合物有几个优势,主要是由于其固有的抗永久性损伤能力和通过多个通道散热的能力,从而提高了全氟化合物的弹性和寿命。本文研究了液态锡(Sn)毛细管多孔系统(CPS)靶在OLMAT高热通量(HHF)设施中暴露于高能粒子束下的热行为。为了获得精确的目标温度测量值,开发了一种迭代校准方法,考虑到由于侵蚀锡的逐枪沉积而导致的诊断窗口的金属化,这种效应部分影响了测量值。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Thermal studies of liquid tin capillary porous system at the OLMAT high heat flux facility
Extreme heat and particle fluxes at the divertor tiles of a fusion device present one of the most critical challenges in achieving sustainable fusion energy. Solid plasma-facing components (PFCs) typically suffer from cracking, erosion, and melting, particularly during transient events, limiting their durability and effectiveness. In contrast, liquid metal PFCs may offer several advantages over their solid counterparts, primarily through their intrinsic resistance to permanent damage and the ability to dissipate heat via multiple channels, thereby enhancing the resilience and longevity of PFCs. This work investigates the thermal behaviour of a liquid tin (Sn) capillary porous system (CPS) target exposed to a high-energy particle beam at the OLMAT high heat flux (HHF) facility. To obtain accurate temperature measurements of the target, an iterative calibration method was developed, accounting for the metallization of the diagnostic window due to the shot-by-shot deposition of eroded Sn, an effect that partially affected the measurements.
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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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