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首页> 外文期刊>International Journal of Pressure Vessels and Piping >Evaluation of mechanical properties distribution for irradiated stainless steels simulated by utilizing the gradient of the cold working ratio
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Evaluation of mechanical properties distribution for irradiated stainless steels simulated by utilizing the gradient of the cold working ratio

机译:利用冷工作率梯度模拟辐射不锈钢力学性能分布的评价

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摘要

It is known that irradiation damage can cause a reduction in fracture toughness and an increase in the strength of austenitic stainless steels used for the internal structures of nuclear power plant reactors. A change in the mechanical properties of material, such as fracture toughness and strength, affects the fracture behavior of the components. Actual reactor internal structures, such as the top guides and core shrouds in BWR plants, are irradiated from the core in a single direction. This causes the attenuation of neutron flux, which results in the distribution of neutron fluence in the components, meaning that the distribution of mechanical properties is in the through-wall direction of the components. It is therefore possible for the fracture mode of the components to change in the through-wall direction. It would be valuable for more accurate assessment of the structural integrity of the nuclear components to make the effect of the mechanical properties distribution on the fracture mode clear. However, it is difficult to prepare large-scale test specimens with the mechanical properties distribution induced by uni-directional neutron irradiation. In this study, the mechanical properties distribution was simulated by applying the gradient of the cold working ratio using Type 316L stainless steel plate with an uneven thickness. The targeted range of the cold working ratio was designed by assuming BWR reactor internal structures, such as the top guides. The mechanical properties distribution was evaluated based on the results of hardness, tensile and fracture toughness tests. It was found that the macroscopic mechanical properties of irradiated stainless steels can be simulated by using the cold working and the macroscopic distribution of the mechanical properties of irradiated stainless steels can also be simulated by using the cold working ratio with a gradient. Furthermore, fracture tests were performed using test plates with the mechanical properties distribution assuming irradiated components with a crack. In some cases, the maximum loads obtained by the tests were almost the same value in spite of the different cold working ratio in the ligament. Based on the results of the fracture tests, it was considered that the dominant mechanical properties for the fracture load were those at the tip of the slit, not those in the ligament.
机译:众所周知,照射损伤会导致骨折韧性的降低和用于核电站反应堆内部结构的奥氏体不锈钢强度的增加。材料的力学性能的变化,例如断裂韧性和强度,影响组分的断裂行为。实际的反应器内部结构,例如BWR植物中的顶部导向器和芯护罩,在单个方向上从芯中照射。这导致中子磁通量的衰减,这导致组件中中子流量的分布,这意味着机械性能的分布在部件的通壁方向上。因此,部件的断裂模式可以改变通壁方向。对核心组分结构完整性的更准确评估对裂缝模式对骨折模式的影响进行更准确的评估将是有价值的。然而,难以制备大规模试验标本,其中通过单向中子辐射诱导的机械性能分布。在该研究中,通过使用型号316L不锈钢板施加具有不均匀厚度的冷加工比的梯度来模拟机械性能分布。通过假设BWR反应器内部结构(例如顶部导向器)设计冷工作比的目标范围。基于硬度,拉伸和断裂韧性试验的结果评价机械性能分布。结果发现,通过使用冷加工可以模拟辐照不锈钢的宏观力学性能,并且还可以通过使用具有梯度的冷工作比来模拟照射不锈钢的机械性能的宏观分布。此外,使用具有裂纹的辐照组分的具有机械性能分布的试验板进行断裂试验。在某些情况下,尽管韧带中的不同冷工作比率,测试获得的最大载荷几乎是相同的值。基于裂缝试验的结果,认为裂缝载荷的主导机械性能是狭缝尖端的主要机械性能,而不是韧带中的裂缝。

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