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Thermo-hydraulic testing and integrity of ITER Test Blanket Module (TBM) First Wall mock-up in JAEA

机译:JAEA中ITER测试毯模块(TBM)第一壁模型的热工液压测试和完整性

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摘要

Fluid flow and heating tests on the full-scale Test Blanket Module (TBM) First Wall (FW) mock-up under the TBM-relevant operating condition were carried out in an ion beam irradiation system with a pressurized high temperature water loop in JAEA to verify the fabrication process and design of the TBM First Wall and demonstrate its heat removal capability. The TBM FW mock-up is made of reduced activation ferritic/martensitic (RAFM) steel, F82H, and its parts such cooling channels and plates were assembled with Hot Isostatic Pressing (HIP) method. In the fluid flow test, the cooling water at room temperature is supplied to 15 parallel flow paths in the mock-up. The flow distribution in each path inside the First Wall mock-up is compared with a numerical simulation. This result shows that no severe cross-sectional deformation of the entire flow path in the mock-up takes place during the fabrication process. In the heating test, the mock-up was exposed to repetitive hydrogen ion beam irradiation with the maximum heat flux of 0.5 MW/m~2. No indication of joint defect of the HIP joint like a hot spot was observed during 80 irradiation cycles.
机译:在与TBM相关的工作条件下,在具有加压高温水回路的离子束辐照系统中,对全尺寸的测试毯模块(TBM)第一壁(FW)样机进行了流体流动和加热测试,以达到加压的目的。验证TBM第一壁的制造工艺和设计,并证明其散热能力。 TBM FW样机由还原活化铁素体/马氏体(RAFM)钢F82H制成,其零件(如冷却通道和板)采用热等静压(HIP)方法组装。在流体流动测试中,将室温下的冷却水供应至模型中的15条平行流路。将第一壁模型中每个路径中的流量分布与数值模拟进行比较。该结果表明,在制造过程中,模型中的整个流路没有发生严重的横截面变形。在加热测试中,将模型暴露于最大热通量为0.5 MW / m〜2的重复氢离子束辐照下。在80个辐照周期中未观察到HIP关节像热点一样的关节缺损迹象。

著录项

  • 来源
    《Fusion Engineering and Design》 |2010年第9期|p.1255-1260|共6页
  • 作者单位

    Fusion Research and Development Directorate, Japan Atomic Energy Agency, 801 Mukoyama, Naka-shi, Ibaraki-ken 311-0193, Japan;

    Fusion Research and Development Directorate, Japan Atomic Energy Agency, 801 Mukoyama, Naka-shi, Ibaraki-ken 311-0193, Japan;

    Fusion Research and Development Directorate, Japan Atomic Energy Agency, 801 Mukoyama, Naka-shi, Ibaraki-ken 311-0193, Japan;

    Fusion Research and Development Directorate, Japan Atomic Energy Agency, 801 Mukoyama, Naka-shi, Ibaraki-ken 311-0193, Japan;

    Fusion Research and Development Directorate, Japan Atomic Energy Agency, 801 Mukoyama, Naka-shi, Ibaraki-ken 311-0193, Japan;

    Fusion Research and Development Directorate, Japan Atomic Energy Agency, 801 Mukoyama, Naka-shi, Ibaraki-ken 311-0193, Japan;

    Fusion Research and Development Directorate, Japan Atomic Energy Agency, 801 Mukoyama, Naka-shi, Ibaraki-ken 311-0193, Japan;

    Fusion Research and Development Directorate, Japan Atomic Energy Agency, 801 Mukoyama, Naka-shi, Ibaraki-ken 311-0193, Japan;

    Fusion Research and Development Directorate, Japan Atomic Energy Agency, 801 Mukoyama, Naka-shi, Ibaraki-ken 311-0193, Japan;

    Fusion Research and Development Directorate, Japan Atomic Energy Agency, 801 Mukoyama, Naka-shi, Ibaraki-ken 311-0193, Japan;

  • 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

    fusion reactor; ITER; blanket; Test Blanket Module (TBM); first wall; pebble bed;

    机译:聚变反应堆;ITER;毯;测试毯模块(TBM);第一壁卵石床;

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