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Effect of the yaw injection angle on the ECC bypass in comparison with the horizontal DVI

机译:与水平DVI相比,偏航喷射角对ECC旁路的影响

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摘要

The comparison tests for the direct emergency core cooling (ECC) bypass fraction were experimentally performed with a typical direct vessel injection (DVI) nozzle and an ECC column nozzle having a yaw injection angle to the gravity axis. The ECC yaw injection nozzle is newly introduced to make an ECC water column in the downcomer region. The yaw injection angle of the ECC water relative to the gravity axis is varied from 0 to (+-)90° stepped by 45°. The tests are performed in the air-water separate effect test facility (direct injection visualization and analysis (DIVA)), which is a 1/7.07 linearly scaled-down model of the APR1400 nuclear reactor. The test results show that (1) if the ECC water column is injected into the wake region which is induced by the hot leg blunt body in the downcomer annulus, the ECC bypass fraction is greatly reduced compared with the typical horizontal ECC injection which makes ECC film on the downcomer wall. At the same time, the ECC penetration toward the lower downcomer region becomes larger than those of a typical horizontal type of direct vessel injection on the downcomer wall vertically. (2) If the ECC water column is injected near the broken cold leg, the ECC water is directly bypassed. Thus, the ECC penetration fraction is greatly reduced compared with a typical film type of the horizontal ECC injection. (3) In order to minimize the ECC bypass fraction, the ECC water should be injected toward the wake region of the hot leg blunt bodies.
机译:使用典型的直接容器注入(DVI)喷嘴和与重力轴具有偏航角的ECC立柱喷嘴,对直接紧急堆芯冷却(ECC)旁路馏分进行了对比测试。 ECC偏航喷射喷嘴是新引入的,用于在降液管区域制造ECC水柱。 ECC水相对于重力轴的偏航喷射角从0到(+-)90°步进45°。测试是在空气-水分离效应测试设备(直接注入可视化和分析(DIVA))中进行的,该设备是APR1400核反应堆的1 / 7.07线性缩小模型。试验结果表明:(1)如果将ECC水柱注入到降液管环空中热腿钝体引起的尾流区域,则与使ECC成水平方向的典型水平ECC注入相比,ECC旁路分数大大降低。电影在降液管的墙上。同时,朝向下部下降管区域的ECC穿透变得比在下降管壁上垂直注入的典型水平型直接血管的ECC穿透更大。 (2)如果将ECC水柱注入破碎的冷段附近,则会直接旁路ECC水。因此,与水平ECC注入的典型薄膜类型相比,ECC渗透率大大降低。 (3)为了使ECC旁路比例最小,应将ECC水注入热腿钝体的尾流区域。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2003年第3期|p.295-304|共10页
  • 作者单位

    Thermal Hydraulic Safety Research Team, Korea Atomic Energy Research Institute, 150 Duckjin-Dong, Yuseong-Ku, Daejeon 305-353, South Korea;

  • 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 原子能技术;
  • 关键词

  • 入库时间 2022-08-18 00:49:01

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