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Investigation of failure behavior of two different types of Zircaloy clad tubes used as nuclear reactor fuel pins

机译:两种不同类型的Zircaloy复合管用作核反应堆燃料销的失效行为研究

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Nuclear reactor fuel pins act as barriers to the release of radioactive fission products to the coolant flowing around these thin-walled tubes and hence they prevent the leakage of radioactivity to the surroundings of reactor core. These tubes are of small thickness in order to have less resistance in the path of heat flow from the fuel to the coolant. Investigation of failure behavior of these fuel clad tubes is of utmost importance to the designers and plant operators in order to ensure the maximum residence time of the fuel bundles inside the reactor core as well as to ensure minimal activity during operation and refueling activities. Various types of zirconium based alloys are used to manufacture these pins. The focus is to obtain better strength, ductility, corrosion resistance, oxidation resistance, and minimal creep including those due to irradiation-assisted damage and deformation processes. Two number of such types of alloys, namely, re-crystallization annealed Zircaloy-2 and stress-relief annealed Zircaloy-4, have been investigated in this work for their fracture behavior. As standard fracture mechanics specimens cannot be machined from these thin-walled tubes, non-standard specimens with axial cracks have been used in this work. Load normalization technique has been used to evaluate crack growth during loading of these specimens. It was observed that the re-crystallization annealed Zircaloy-2 specimens have higher initiation fracture toughness as well as higher resistance to crack growth compared to the other type of specimens. In order to understand the micro-structural aspects of the fracture resistance behavior of these materials, further investigation incorporating optical and transmission electron microscopy have also been carried out. It was concluded that the higher fracture resistance behavior of the re-crystallization annealed Zircaloy-2 specimens can be attributed to the presence of finer grain and sub-grain micro-structure, very low dislocation density and other defects in the material.
机译:核反应堆燃料销钉是阻止放射性裂变产物释放到围绕这些薄壁管流动的冷却剂的屏障,因此,它们可防止放射性泄漏到反应堆堆芯周围。这些管的厚度较小,以便在从燃料到冷却剂的热流路径中具有较小的阻力。为了确保燃料束在反应堆堆芯内的最大停留时间,并确保在运行和加油活动中的活动最少,对设计人员和工厂操作人员而言,研究这些燃料包层管的故障行为至关重要。各种类型的锆基合金用于制造这些销。重点是获得更好的强度,延展性,耐腐蚀性,抗氧化性以及最小的蠕变,包括那些由于辐射辅助的损伤和变形过程而产生的蠕变。在这项工作中,已经研究了两种类型的合金,即再结晶退火Zircaloy-2和应力消除退火Zircaloy-4,其断裂行为。由于无法从这些薄壁管中加工出标准的断裂力学试样,因此在这项工作中使用了具有轴向裂纹的非标准试样。载荷归一化技术已用于评估这些样品在加载过程中的裂纹扩展。观察到,与其他类型的样品相比,经过再结晶退火的Zircaloy-2样品具有更高的初始断裂韧性以及更高的抗裂纹扩展性。为了理解这些材料的抗断裂性能的微观结构方面,还进行了结合光学和透射电子显微镜的进一步研究。结论是,再结晶退火的Zircaloy-2试样的较高的抗断裂性能可归因于存在更细的晶粒和亚晶粒的微观结构,极低的位错密度以及材料中的其他缺陷。

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