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首页> 外文期刊>Проблемы прочностиПроблемы прочности: на рус.укр.и анг.языках >Prediction of crack growth resistance for ductile fracture of neutron-irradiated reactor pressure-vessel steels. part 1
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Prediction of crack growth resistance for ductile fracture of neutron-irradiated reactor pressure-vessel steels. part 1

机译:中子辐照反应器压力容器钢延性骨折裂纹生长抗性的预测。 第1部分

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摘要

Theoretical foundations of modeling of the neutron irradiation effect on the level of the upper shelf of the dependence K{sub}(1c)(T) were considered. Modeling involves the application of the local criterion and ductile fracture model suggested by the authors previously. A physical interpretation of the irradiation effect on mechanisms governing ductile fracture was given. Parameters of the model, which are sensitive to the neutron irradiation, were determined.
机译:考虑了对依赖性k {}(1c)(T)的上架水平的中子辐射效应建模的理论基础。 建模涉及以前提出的本地标准和延性裂缝模型的应用。 给出了治疗延性骨折机制的辐照效应的物理解释。 确定了对中子辐射敏感的模型的参数。

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