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Simulation of J{sub}R-curves for reactor pressure vessels steels on the basis of a ductile fracture model

机译:基于延性断裂模型的反应堆压力容器钢J {sub} R曲线的模拟

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摘要

A procedure for the prediction of J{sub}R-curves for reactor pressure vessels (RPVs) steels in the initial and embrittled states is presented. Prediction of the J{sub}R-curves is performed over the ductile fracture temperature range on the basis of a ductile fracture model. A procedure for the determination of ductile fracture model parameters based on tests of smooth and notched cylindrical specimens is proposed. The stress and strain fields near the stationary and growing crack tip are analyzed by FEM. Approximate analytical solutions for stress and strain fields near a growing crack tip are proposed. Comparison of the predicted J{sub}R-curves and experimental 2T-CT data for the initial and embrittled RPV 2Cr-Ni-Mo-V steels for WWER-1000 is performed.
机译:提出了一种用于预测反应堆压力容器(RPV)钢在初始和脆化状态下的J {sub} R曲线的程序。基于延性断裂模型,在延性断裂温度范围内进行J {sub} R曲线的预测。提出了一种基于光滑有缺口的圆柱试样的试验确定延性断裂模型参数的程序。通过有限元分析,分析了固定和增长裂纹尖端附近的应力和应变场。提出了裂纹尖端附近应力场和应变场的近似解析解。对WWER-1000的RPV 2Cr-Ni-Mo-V初始和脆性RPV钢的预测J {sub} R曲线和实验2T-CT数据进行了比较。

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