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TOKAMAK DISCHARGE TEST WITH A FERRITIC FIRST WALL SIMULATING VACUUM VESSEL

机译:用铁素体第一壁模拟真空容器进行托卡马克放电试验

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摘要

A plasma discharge experiment, measurements and calculations of the magnetic field in the Hitachi tokamak HT-2rnshowed that ferritic steel is available for the vacuum vessel structural material in fusion devices, in spite of itsrnferromagnetism. The HT-2 has a stainless steel SS304 vacuum vessel and F82H plates were added just like a first wall, tornsimulate a ferritic vacuum vessel. The vacuum quality was not degraded. About 1500 discharge tries cleaned up the F82Hrnand normal discharges was obtained. The magnetic field due to the F82H magnetization was small enough that it did notrncause a problem for plasma discharge in the HT-2. Since the field due to the magnetization is expected to be smaller in largerntokamaks than in the HT-2, we concluded that the ferritic steel can be used as a structural material for fusion devices.
机译:日立托卡马克HT-2rn的等离子体放电实验,磁场的测量和计算表明,铁素体钢尽管具有铁磁性,但仍可用于聚变装置中的真空容器结构材料。 HT-2具有不锈钢SS304真空容器,并且像第一壁一样添加了F82H板,以模拟铁素体真空容器。真空质量没有降低。大约进行了1500次排放尝试以清理F82Hrn,并获得了正常排放。 F82H磁化强度产生的磁场足够小,不会引起HT-2中的等离子体放电问题。由于预计更大的ntokamaks中的磁化场将比HT-2小,因此我们得出结论,铁素体钢可用作融合装置的结构材料。

著录项

  • 来源
    《》|1998年|p.1-4|共4页
  • 会议地点 Yokohama(JP)
  • 作者单位

    Power Industrial Systems R D Division, Hitachi, Ltd.,rn7-2-1, Omika-cho, Hitachi-shi, Ibaraki, Japan;

    rnPower Industrial Systems R D Division, Hitachi, Ltd.,rn7-2-1, Omika-cho, Hitachi-shi, Ibaraki, Japan;

    rnPower Industrial Systems R D Division, Hitachi, Ltd.,rn7-2-1, Omika-cho, Hitachi-shi, Ibaraki, Japan Hitachi works, Hitachi Ltd. Saiwai-cho Hitachi-shi Ibaraki, Japan;

    rnPower Industrial Systems R D Division, Hitachi, Ltd.,rn7-2-1, Omika-cho, Hitachi-shi, Ibaraki, Japan Hitachi works, Hitachi Ltd. Saiwai-cho Hitachi-shi Ibaraki, Japan;

  • 会议组织
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 受控热核反应(聚变反应理论及实验装置);
  • 关键词

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