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Thermo-mechanical design of the Plasma Driver Plate for the MITICA ion source

机译:MITICA离子源的等离子驱动板的热机械设计

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In the framework of the activities for the development of the Neutral Beam Injector (NBI) for ITER, the detailed design of the Radio-Frequency (RF) negative ion source has been carried out. One of the most heated components of the RF source is the rear vertical plate, named Plasma Driver Plate (PDP), where the Back-Streaming positive Ions (BSI+) generated from stripping losses in the accelerator and back scattered on the plasma source impinge on. The heat loads that result are huge and concentrated, with first estimate of the power densities up to 60 MW/m~2. The breakdowns that occur into the accelerator cause such heat loads to act cyclically, so that the PDP is thermo-mechanically fatigue loaded. Moreover, the surface of the PDP facing the plasma is functionally required to be temperature controlled and to be molybdenum or tungsten coated. The thermo-hydraulic design of the plate has been carried out considering active cooling with ultra-pure water. Different heat sink materials, hydraulic circuit layout and manufacturing processes have been considered. The heat exhaust has been optimized by changing the channels geometry, the path of the heat flux in the heat sink, the thickness of the plate and maximizing the Heat Transfer Coefficient. Such optimization has been carried out by utilizing 3D Finite Element (FE) models. Afterwards all the suitable mechanical (aging, structural monotonic and cyclic) verifications have been carried out post-processing the results of the thermo-mechanical 3D FE analyses in accordance to specific procedures for nuclear components exposed to high temperature. The effect of sputtering phenomenon due to the high energy BSI+ impinging on the plate has been considered and combined with fatigue damage for the mechanical verification of the PDP. Alternative solutions having molybdenum (or tungsten coatings) facing the plasma, aiming to reduce the sputtering rate and the consequent plasma pollution, have been evaluated and related 3D FE models have been developed, analyzed and compared. In this paper, the design will be presented in detail, as well as the analyses carried out for the thermo-mechanical verification of the component and an outlook to open issues.
机译:在发展用于ITER的中性束注入器(NBI)的活动框架内,已经进行了射频(RF)负离子源的详细设计。射频源中加热最严重的组件之一是后垂直板,称为等离子驱动器板(PDP),其中加速器中的汽提损耗产生的回流正离子(BSI +)以及等离子源上的反向散射会撞击到。产生的热负荷巨大且集中,首先估计的功率密度高达60 MW / m〜2。加速器中发生的故障会导致此类热负荷循环作用,从而使PDP承受热机械疲劳负荷。而且,在功能上要求PDP的面对等离子体的表面是温度受控的并且需要钼或钨涂覆。考虑到使用超纯水进行主动冷却,对板进行了热工液压设计。已经考虑了不同的散热器材料,液压回路布局和制造工艺。通过改变通道的几何形状,散热片中的热通量路径,板的厚度以及使传热系数最大化来优化散热效果。通过利用3D有限元(FE)模型进行了这种优化。然后,根据暴露在高温下的核组件的特定程序,对热机械3D FE分析的结果进行后处理,然后进行所有合适的机械(老化,结构单调和循环)验证。已经考虑了由于高能BSI +撞击在板上而引起的溅射现象的影响,并与疲劳损伤结合在一起用于PDP的机械验证。为了降低溅射速率和随之而来的等离子体污染,已经评估了具有面向钼的钼(或钨涂层)的替代解决方案,并且已经开发,分析和比较了相关的3D FE模型。在本文中,将详细介绍设计,以及对组件进行热机械验证的分析以及对未解决问题的展望。

著录项

  • 来源
    《Fusion Engineering and Design》 |2010年第9期|p.1073-1079|共7页
  • 作者单位

    Consorzio RFX, EURATOM-ENEA Association, Corso Stati Uniti 4,1-35127 Padova. Italy;

    Consorzio RFX, EURATOM-ENEA Association, Corso Stati Uniti 4,1-35127 Padova. Italy;

    Consorzio RFX, EURATOM-ENEA Association, Corso Stati Uniti 4,1-35127 Padova. Italy;

  • 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

    ITER; NBI; ion source;

    机译:ITER;NBI;离子源;

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