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Fracture experiments on through wall cracked elbows under in-plane bending moment; test results and theoreticalumerical analyses

机译:面内弯矩作用下贯穿壁裂纹肘部的断裂实验;测试结果和理论/数值分析

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Fracture assessment of pipe bends or elbows with postulated through wall crack is very essential for leak-before-break qualification of primary heat transport system piping of nuclear power plants. The methodology for fracture assessment of cracked elbows is still in developing stage. Any new development in theoretical aspect requires experimental validation. However, fracture test data on cracked elbows is not so abundant as straight pipes. The earlier experiments on cracked elbows were focused mainly on the determination of limit load. Other fracture parameters e.g. crack growth, crack initiation load or crack opening displacement were not reported in the open literature. Against this backdrop, a comprehensive experimental and theoretical program on component integrity has been initiated at Reactor Safety Division (RSD) of Bhabha Atomic Research Center (BARC), India. Under this program, a number of fracture tests have been carried out on elbows with through wall circumferential/axial cracks subjected to in-plane closing/opening bending moment. These test data are then thoroughly analysed numerically through non-linear finite element analyses, analytically through limit load comparison and also through comparison of crack initiation loads by finite element and R6 methods. These test data may be utilized in future for validation of new theoretical developments in the integrity assessment of through wall cracked elbows.
机译:假定通过壁裂纹的弯管或弯头的断裂评估对于核电厂一次热传输系统管道的破损检漏非常重要。裂纹肘部骨折的评估方法仍处于发展阶段。理论上的任何新发展都需要实验验证。但是,破裂的肘部的断裂试验数据不如直管那么丰富。裂纹肘部的早期实验主要集中在极限载荷的确定上。其他断裂参数例如公开文献中没有报道裂纹扩展,裂纹起始载荷或裂纹开口位移。在此背景下,印度Bhabha原子研究中心(BARC)的反应堆安全部(RSD)已启动了有关组件完整性的全面实验和理论计划。在该程序下,已经对肘部进行了多次断裂试验,其中,贯穿壁的周向/轴向裂纹受到平面内闭合/打开弯曲力矩的影响。然后,通过非线性有限元分析,极限载荷比较以及有限元和R6方法对裂纹萌生载荷的比较,对这些测试数据进行数值分析。这些测试数据可在将来用于验证贯穿壁开裂弯头的完整性评估中的新理论发展。

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