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The integral analysis of 40 mm diameter pipe rupture in cooling system of fusion facility W7-X with ASTEC code

机译:W7-X聚变设施冷却系统中直径40 mm的管道破裂的整体分析,采用ASTEC规范

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摘要

Fusion is the energy production technology, which could potentially solve problems with growing energy demand of population in the future. Wendelstein 7-X (W7-X) is an experimental facility of stellarator type, which is currently being built at the Max-Planck-Institute for Plasmaphysics located in Greifswald, Germany. W7-X shall demonstrate that in future the energy could be produced in such type of fusion reactors. The safety analysis is required before the operation of the facility could be started. A rupture of 40 mm diameter pipe, which is connected to the divertor unit (module for plasma cooling) to ensure heat removal from the vacuum vessel in case of no-plasma operation mode "baking" is one of the design basis accidents to be investigated. During "baking" mode the vacuum vessel structures and working fluid - water are heated to the temperature 160 degrees C. This accident was selected for the detailed analysis using integral code ASTEC, which is developed by IRSN (France) and GRS mbH (Germany).
机译:聚变是一种能源生产技术,它有可能在将来解决人口能源需求不断增长的问题。 Wendelstein 7-X(W7-X)是恒星类型的实验设备,目前正在德国格赖夫斯瓦尔德的Max-Planck等离子体物理研究所建造。 W7-X必须证明,将来这种类型的聚变反应堆可能会产生能量。在开始设施运行之前,必须进行安全分析。连接至分流器单元(等离子冷却模块)的直径为40 mm的管道破裂,以确保在无等离子操作模式“烘烤”的情况下从真空容器中散热,这是要研究的设计依据事故之一。在“烘焙”模式下,真空容器的结构和工作流体(水)被加热到160摄氏度。使用IRTC(法国)和GRS mbH(德国)开发的完整代码ASTEC选择了该事故进行详细分析。

著录项

  • 来源
    《Fusion Engineering and Design》 |2015年第12期|141-147|共7页
  • 作者单位

    Lithuanian Energy Inst, Lab Nucl Installat Safety, LT-44403 Kaunas, Lithuania;

    Lithuanian Energy Inst, Lab Nucl Installat Safety, LT-44403 Kaunas, Lithuania;

  • 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

    ASTEC; W7-X; LOCA;

    机译:ASTEC;W7-X;LOCA;

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