首页> 外文期刊>International Journal of Pressure Vessels and Piping >Radiation embrittlement modelling for reactor pressure vessel steels: II. ductile fracture toughness prediction
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Radiation embrittlement modelling for reactor pressure vessel steels: II. ductile fracture toughness prediction

机译:反应堆压力容器钢的辐射脆化模型:II。韧性断裂韧性预测

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摘要

Modelling for the irradiation effect on ductile fracture toughness of reactor pressure vessel steels (RPV) is performed on the basis of ductile fracture criterion proposed earlier by the authors. The irradiation effect on mechanisms controllingductile fracture is considered from a physical viewpoint. Modelling of the irradiation effect is carried out on the critical strain for smooth cylindrical specimens and on the local critical strain for cracked specimens. On the basis of the performedstudies a scheme that allows an evaluation of the upper shelf level of the K{sub}(IC)(T) curve for irradiated RPV steels is proposed.
机译:基于作者先前提出的延性断裂准则,对反应堆压力容器钢(RPV)的延展性断裂韧性进行了辐照效果建模。从物理角度考虑了辐射对控制延性断裂的机理的影响。对光滑圆柱样品的临界应变和破裂样品的局部临界应变进行辐射效果建模。在进行的研究的基础上,提出了一种方案,该方案可以评估辐照的RPV钢的K {sub}(IC)(T)曲线的上层货架水平。

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