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Failure modeling of a nuclear pressure pipe with a shallow surface flaw

机译:浅层表面缺陷的核压管故障建模

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Shallow surface cracks in nuclear pressure pipes have been recognized as a major origin of potential catastrophic failure for such components. Failure assessment has been done currently by a one-parameter fracture mechanics approach. The J-integral is the one-parameter used, and has been proved to be useful to predict ductile crack initiation. However, when shallow surface and/or a fully plastic condition develops around the crack, the J-integral alone does'not describe completely the crack tip stress field and a second parameter is necessary. In this paper, a modeling of the three-dimensional elastic-plastic stress field around a crack tip is used to evaluate a second fracture parameter Q. This parameter measures the degree of triaxiality around the crack tip and is very important in a two-parameter fracture mechanics approach. The defect considered in the pipe is a three-dimensional shallow surface crack. The Finite Element Method is used to evaluate the full crack-tip stress field. The material, an ASTM A 516 Gr. 70 steel used in the nuclear industry, is modeled with a Ramberg-Osgood power law and flow theory of plasticity. A finite deformation theory was used to account for the highly nonlinear behavior around the crack tip. Numerical results are presented for the J integral parameter, normal stress in the very near crack-tip and for the second parameter Q, for a wide applied pressure loading in the flawed pipe.
机译:核压管中的浅表面裂缝已被认为是这种组件的潜在灾难性失效的主要起源。失败评估目前是通过一次参数裂缝力学方法进行的。 J-Integral是所用的一个参数,并且已被证明是有用的可用于预测延性裂纹启动。然而,当浅表面和/或完全塑性的条件围绕裂缝发生时,单独的J-IntegleAte NOT完全描述裂缝尖端应力场,并且需要第二个参数。在本文中,使用裂缝尖端周围的三维弹性塑性应力场的建模来评估第二裂缝参数Q.该参数测量裂纹尖端周围的三轴性程度,在两个参数中非常重要裂缝力学方法。管道中考虑的缺陷是三维浅表面裂缝。有限元方法用于评估全裂纹尖端应力场。材料,ASTM A 516 GR。核工业中使用的70钢材,采用Ramberg-Osgood电力法和流量的可塑性模拟。有限变形理论用于考虑裂缝尖端周围的高度非线性行为。为氮气管中的宽施加压力负载呈现近近裂纹尖端和第二参数Q的j积分参数,正常应力,呈现数值结果。

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