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Plasma-wall interaction studies within the EUROfusion consortium: Progress on plasma-facing components development and qualification

机译:EUROfusion联盟内的等离子-壁相互作用研究:等离子组件的开发和认证进展

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摘要

The provision of a particle and power exhaust solution which is compatible with first-wall components and edge-plasma conditions is a key area of present-day fusion research and mandatory for a successful operation of ITER and DEMO. The work package plasma-facing components (WP PFC) within the European fusion programme complements with laboratory experiments, i.e. in linear plasma devices, electron and ion beam loading facilities, the studies performed in toroidally confined magnetic devices, such as JET, ASDEX Upgrade, WEST etc. The connection of both groups is done via common physics and engineering studies, including the qualification and specification of plasma-facing components, and by modelling codes that simulate edge-plasma conditions and the plasma-material interaction as well as the study of fundamental processes. WP PFC addresses these critical points in order to ensure reliable and efficient use of conventional, solid PFCs in ITER (Be and W) and DEMO (W and steel) with respect to heat-load capabilities (transient and steady-state heat and particle loads), lifetime estimates (erosion, material mixing and surface morphology), and safety aspects (fuel retention, fuel removal, material migration and dust formation) particularly for quasi-steady-state conditions. Alternative scenarios and concepts (liquid Sn or Li as PFCs) for DEMO are developed and tested in the event that the conventional solution turns out to not be functional. Here, we present an overview of the activities with an emphasis on a few key results: (i) the observed synergistic effects in particle and heat loading of ITER-grade W with the available set of exposition devices on material properties such as roughness, ductility and microstructure; (ii) the progress in understanding of fuel retention, diffusion and outgassing in different W-based materials, including the impact of damage and impurities like N; and (iii), the preferential sputtering of Fe in EUROFER steel providing an in situ W surface and a potential first-wall solution for DEMO.
机译:提供与第一壁组件和边缘等离子体条件兼容的粒子和动力排放解决方案是当今融合研究的关键领域,并且对于ITER和DEMO的成功运行必不可少。欧洲聚变计划中的工作包等离子组件(WP PFC)与实验室实验相辅相成,即在线性等离子设备,电子和离子束加载设备中,在环形受限磁设备中进行的研究,例如JET,ASDEX升级, WEST等。两组的连接是通过普通的物理学和工程学研究(包括等离子组件的鉴定和规范)以及通过模拟边缘等离子条件和等离子-材料相互作用的建模代码以及基本过程。 WP PFC解决了这些关键点,以确保在热负荷能力(瞬态和稳态热负荷和颗粒负荷)方面,在ITER(Be和W)和DEMO(W和钢)中可靠有效地使用常规固态PFC。 ),寿命估算值(腐蚀,材料混合和表面形态)以及安全性方面(燃料保留,燃料去除,材料迁移和粉尘形成),尤其是在准稳态条件下。在传统解决方案无法正常工作的情况下,将开发和测试用于DEMO的替代方案和概念(液态Sn或Li作为PFC)。在这里,我们对活动进行了概述,并着重介绍了一些关键结果:(i)使用可用的曝光设备对材料性能(例如粗糙度,延展性)可用的ITER级W颗粒和热负荷的协同效应和微观结构; (ii)在了解基于W的不同材料中的燃料滞留,扩散和除气方面的进展,包括损害和杂质(如N)的影响; (iii)在EUROFER钢中优先溅射Fe,可提供原位W表面和潜在的DEMO第一壁解决方案。

著录项

  • 来源
    《Nuclear fusion》 |2017年第11期|116041.1-116041.9|共9页
  • 作者单位

    Forschungszentrum Jülich GmbH, Institut für Energie und Klimaforschung - Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), Jülich, Germany;

    Forschungszentrum Jülich GmbH, Institut für Energie und Klimaforschung - Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), Jülich, Germany;

    Max-Planck-Institut für Plasmaphysik, Garching, Germany;

    Max-Planck-Institut für Plasmaphysik, Garching, Germany;

    Forschungszentrum Jülich GmbH, Institut für Energie und Klimaforschung - Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), Jülich, Germany;

    @;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    beryllium; particle exhaust; plasma-facing components; plasma-surface interaction; power exhaust; tungsten;

    机译:铍;颗粒排气等离子组件;等离子体-表面相互作用;动力排气钨;
  • 入库时间 2022-08-18 00:41:41

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