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Evaluation of Quasi-Static and Dynamic Fracture Toughness on the Low-Alloy Reactor Pressure Vessel Steel JRQ in the Transition Region

机译:在过渡区中低合金反应器压力容器钢JRQ对准静态和动态断裂韧性的评价

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Three point bending and impact tests with sub-sized Charpy specimens were performed on the JRQ reference steel for reactor pressure vessels. Quasi-static and dynamic fracture toughness data were calculated and the fracture behavior in the ductile to brittle transition region was evaluated within the frame of the master curve method (ASTM E1921). Specimens with shallow and deep cracks were studied and the respective influence of crack length and loading rate on the reference transition temperature was determined. The force-time curves of specimens with shallow cracks presented significantly smaller oscillations with respect to the absolute force, making the fracture toughness evaluation more accurate.
机译:在JRQ参考钢上对反应器压力容器进行三点弯曲和冲击试验。计算准静态和动态断裂韧性数据,并在主曲线法的框架内评估延性到脆性转变区域的断裂行为(ASTM E1921)。研究了具有浅和深裂缝的标本,测定裂缝长度和加载率对参考转变温度的各自影响。具有浅裂缝的试样的力时间曲线对于绝对力表示明显较小的振荡,使得断裂韧性评估更准确。

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