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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >A study of life prediction differences for a nickel-base Alloy 690 using a threshold and a non-threshold model
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A study of life prediction differences for a nickel-base Alloy 690 using a threshold and a non-threshold model

机译:使用阈值和非阈值模型研究镍基合金690的寿命预测差异

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In this paper we compare and contrast the crack growth rate of a nickel-base superalloy (Alloy 690) in the Pressurized Water Reactor (PWR) environment. Over the last few years, a preponderance of test data has been gathered on both Alloy 690 thick plate and Alloy 690 tubing. The original model, essentially based on a small data set for thick plate, compensated for temperature, load ratio and stress-intensity range but did not compensate for the fatigue threshold of the material. As additional test data on both plate and tube product became available the model was gradually revised to account for threshold properties. Both the original and revised models generated acceptable results for data that were above I x 10(-11) m/s. However, the test data at the lower growth rates were over-predicted by the non-threshold model. Since the original model did not take the fatigue threshold into account, this model predicted no operating stress below which the material would effectively undergo fatigue crack growth. Because of an over-prediction of the growth rate below 1 x 10(-11) m/s, due to a combination of low stress, small crack size and long rise-time, the model in general leads to an under-prediction of the total available life of the components.
机译:在本文中,我们比较和对比了压水堆(PWR)环境中镍基高温合金(Alloy 690)的裂纹扩展速率。在过去的几年中,在690合金厚板和690合金管上都收集了大量的测试数据。原始模型主要基于厚板的少量数据集,补偿了温度,负载比和应力强度范围,但没有补偿材料的疲劳阈值。随着板和管产品的更多测试数据变得可用,该模型逐渐修订以考虑阈值特性。原始模型和经修订的模型都为I x 10(-11)m / s以上的数据生成了可接受的结果。但是,较低阈值的测试数据被非阈值模型高估了。由于原始模型没有考虑疲劳阈值,因此该模型预测没有操作应力,低于此应力,材料将有效地发生疲劳裂纹扩展。由于低应力,小裂纹尺寸和长上升时间的共同作用,导致对增长率低于1 x 10(-11)m / s的过度预测,因此该模型通常会导致对组件的总可用寿命。

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