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本文的工程方法,是文献[1]工作的进一步发展。主要用来解决核电站的带非贯穿裂纹压力壳的剩余破坏强度的计算问题。为了向核电站压力壳的研究、设计、制造和使用者们表明这个方法是可靠的,对美国原子能委员会近十几年试验研究过的压水堆(或沸水堆)的带裂纹压力壳进行了计算分析,并且和试验结果作了详细比较。裂纹无论在压力壳简体的母材上、焊缝上或接管内拐角上,计算和试验结果都符合得比较好。另外,还对作者搜集到的内壁中子(大于1兆电子伏)通量累积峰值达1.6×10~(19)中子/厘米~2的已作过断裂试验的PM-2A压力壳进行了分析计算和讨论。
The engineering method of this article is the further development of the literature [1]. Mainly used to solve the nuclear power plant with non-through the crack pressure shell of the remaining damage strength calculation problems. In order to study, design, manufacture and use the pressure shell of the nuclear power plant, this method is proved to be reliable. The cracked pressure shell of PWR (or boiling water reactor), which has been researched and researched by the Atomic Energy Commission for nearly ten years, has been calculated Analysis, and a detailed comparison with the test results. Crack Whether in the pressure vessel Simplified base metal, weld or take over the corner, the calculation and test results are in good agreement. In addition, PM-2A pressure hull, which has been subjected to the fracture test, was also collected for the collected neutron neutron (more than 1 mega-electron volts) flux peaked at 1.6 × 10 19 neutron / cm 2 Analysis and calculation and discussion.