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Application of the Probabilistic Fatigue Evaluation of Flow-Induced Vibration for Hot-Leg Piping in Japan Sodium-Cooled Fast Reactor

机译:流动疲劳振动概率疲劳评估在日本钠冷快堆中的应用

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摘要

The primary hot-leg piping system of the advanced sodium-cooled fast reactor under conceptual study in Japan (named Japan sodium-cooled fast reactor: JSFR) utilizes large-diameter and thin-walled pipes to ensure high coolant velocity, which inevitably leads to the occurrence of flow-induced vibration. Usually, the structural integrity of a piping system under flow-induced vibration is defined to be the maximum stress amplitude below the design fatigue limit. The present study tries to establish a reasonable methodology to estimate the high-cycle fatigue damage due to flow-induced vibration depending on its frequencies and the corresponding stress levels. An analytical procedure for probabilistic fatigue evaluation is developed and applied to the hot-leg piping system. The reasonability of the newly proposed methodology is confirmed from a test simulation.
机译:在日本进行概念研究的先进钠冷快堆主要热管系统(称为日本钠冷快堆:JSFR)利用大直径和薄壁管道来确保高冷却液速度,这不可避免地导致流动引起的振动的发生。通常,将管道系统在流动引起的振动下的结构完整性定义为低于设计疲劳极限的最大应力振幅。本研究试图建立一种合理的方法来估算由于流动引起的振动而引起的高周疲劳损伤,具体取决于其频率和相应的应力水平。开发了一种用于概率疲劳评估的分析程序,并将其应用于热腿管道系统。新的方法论的合理性已通过测试仿真得到证实。

著录项

  • 来源
    《Nuclear science and engineering》 |2014年第1期|76-85|共10页
  • 作者单位

    Mitsubishi FBR Systems, Inc. 34-17, Jingu-Mae, 2-chome, Shibuya-ku, Tokyo, 150-0001, Japan;

    Mitsubishi FBR Systems, Inc. 34-17, Jingu-Mae, 2-chome, Shibuya-ku, Tokyo, 150-0001, Japan;

    Mitsubishi FBR Systems, Inc. 34-17, Jingu-Mae, 2-chome, Shibuya-ku, Tokyo, 150-0001, 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

  • 入库时间 2022-08-18 00:42:57

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