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Design, manufacture and initial operation of the beryllium components of the JET ITER-like wall

机译:类似于JET ITER墙的铍组件的设计,制造和初始操作

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摘要

The aim of theJET ITER-like wall project was to provide JET with the plasma facing material combination now selected for the DT phase of ITER (bulk beryllium main chamber limiters and a full tungsten divertor) and, in conjunction with the upgraded neutral beam heating system, to achieve ITER relevant conditions. The design of the bulk Be plasma facing components had to be compatible with increased heating power and pulse length, as well as to reuse the existing tile supports originally designed to cope with disruption loads from carbon based tiles and be installed by remote handling. Risk reduction measures (prototypes, jigs, etc.) were implemented to maximize efficiency during the shutdown. However, a large number of clashes with existing components not fully captured by the configuration model occurred. Restarting the plasma on the ITER-like Wall proved much easier than for the carbon wall and no decon-ditioning by disruptions was observed. Disruptions have been more threatening than expected due to the reduced radiative losses compared to carbon, leaving most of the plasma magnetic energy to be conducted to the wall and requiring routine disruption mitigation. The main chamber power handling has achieved and possibly exceeded the design targets.
机译:类似于JET的ITER墙项目的目的是为JET提供现选用于ITER DT阶段的等离子体处理材料组合(铍主腔限流器和全钨分流器),并与升级的中性束加热系统结合使用,以达到ITER相关条件。大块Be等离子体表面组件的设计必须与增加的加热功率和脉冲长度兼容,并且必须重新使用现有的瓷砖支架,该支架最初设计用于应对碳基瓷砖的破坏负荷,并需要通过远程操作进行安装。实施了降低风险的措施(原型,夹具等),以在关闭期间最大程度地提高效率。但是,与配置模型未完全捕获的现有组件发生了大量冲突。在类似ITER的壁上重新启动等离子体比在碳壁上重新启动要容易得多,并且没有观察到因干扰而引起的分解。与碳相比,由于辐射损失减少,破坏比预期的更具威胁性,大部分等离子磁能被传导到壁上,需要常规的破坏缓解措施。主腔室的功率处理已经达到并可能超出了设计目标。

著录项

  • 来源
    《Fusion Engineering and Design》 |2013年第8期|585-589|共5页
  • 作者单位

    EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon, OX14 3DB, UK,JET-EFDA, Culham Science Centre, Abingdon, OX14 3DB, UK;

    EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon, OX14 3DB, UK,JET-EFDA, Culham Science Centre, Abingdon, OX14 3DB, UK;

    EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon, OX14 3DB, UK,JET-EFDA, Culham Science Centre, Abingdon, OX14 3DB, UK;

    Associacao EURATOM-IST, IPFN - Laboratorio Associado, IST, Lisbon, Portugal,JET-EFDA, Culham Science Centre, Abingdon, OX14 3DB, UK;

    EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon, OX14 3DB, UK,JET-EFDA, Culham Science Centre, Abingdon, OX14 3DB, UK;

    CEA IRFM, F-13108 Saim-Paul-lez-Durance, France,JET-EFDA, Culham Science Centre, Abingdon, OX14 3DB, UK;

  • 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; Plasma facing components; JET; Power handling; Disruption loads;

    机译:铍;等离子组件;喷射;电源处理;破坏负荷;

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