首页> 外文会议>PVP2011;ASME Pressure Vessels and Piping conference >ANALYSIS OF THE THERMAL FATIGUE CRACKING OF 316L MODEL PIPE COMPONENTS AT FAST REACTOR TEMPERATURES
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ANALYSIS OF THE THERMAL FATIGUE CRACKING OF 316L MODEL PIPE COMPONENTS AT FAST REACTOR TEMPERATURES

机译:快速反应器温度下316L模型管件的热疲劳开裂分析

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In order to assess the high-cycle thermal fatigue damage risk of the nuclear power plants mixing zones, the knowledge of the temperature fluctuations effect on the structure surface is necessary. To advance the accuracy and reliability of thermal fatigue load determination, a combined experimental and numerical investigation has been conducted on cylindrical components of 316L stainless steel subject to cyclic thermal shocks of varying intensity. Slightly different experimental conditions were applied in each test to explore the effect of ΔT_(max) values of increasing severity, addressing also higher temperatures typical for fast reactors, the effect of a superimposed static axial load to study the effect of a constant pressure on the thermal fatigue damage and a reduced test piece wall thickness. A comparison between thermal down-shock tests with and without additional constant tensile load and with different maximum temperatures are analysed in details here below.
机译:为了评估核电站混合区的高循环热疲劳破坏风险,必须了解温度波动对结构表面的影响。为了提高热疲劳载荷确定的准确性和可靠性,已经对经受不同强度的循环热冲击的316L不锈钢圆柱部件进行了组合的实验和数值研究。在每个测试中应用了略有不同的实验条件,以探索增加严重性的ΔT_(max)值的影响,还解决了快速反应堆的典型较高温度,叠加的静态轴向载荷的影响,以研究恒定压力对反应堆的影响。热疲劳损伤和减小的试件壁厚。下面详细分析了在有和没有附加恒定拉伸载荷以及有不同最高温度的情况下进行热冲击试验的比较。

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