反应堆压力容器入口接管焊缝超声不可达区域非线性研究

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压水反应堆压力容器入口(Inlet)接管与筒体对接焊缝具有复杂的几何体特征,且焊缝超声检查区域在多种在役检查规范中定义不一致,这些因素导致其不可达区域呈非线性变化。为研究该区域的特殊变化规律,建立了Inlet接管与筒体焊缝参数模型,分析坡面特征导致的不可达区域仿真方法和分类判别法则。基于该法则,结合美国机械工程师学会(ASME)规范与核电厂相关参数,运用三维仿真软件采集接管组件不可达区域体积离散数据集,求取出左、右不可达区体积占比-超声折射角关系图,并介绍占比指标在相控阵和常规超声工艺的应用和优化方法。本研究以减少不可达区域并提高缺陷发现概率为目的,特别适用于相控阵和常规超声工艺在此类焊缝的不可达性和分布规律的数理研究。 Complicated geometric features of PWR inlet inlets and barrel butt welds and inconsistencies in weld ultrasound examination areas defined in a number of in-service inspection specifications have resulted in non-linear changes in their unreachable area . In order to study the special variation law in this area, the parameters model of Inlet pipe joint and barrel weld were established, and the non-reachable area simulation method and classification discrimination rule caused by slope characteristics were analyzed. Based on the law, combining with ASME’s specification and nuclear power plant’s parameters, using 3D simulation software to collect discrete data sets of the unreachable area volume of the takeover assembly, the relationship between the volume fraction of the left and right unreachable areas and the ultrasonic refraction angle Figure, and introduce the proportion of indicators in phased array and conventional ultrasonic application and optimization methods. The purpose of this study is to reduce the unreachable area and improve the probability of defect detection, which is especially suitable for the mathematical research on the inaccessibility and distribution of such weld by phased array and conventional ultrasonic welding.
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