低温锆合金-2的拉伸性能

P. A. R. Kamalanath, A. Sarkar
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引用次数: 11

摘要

锆-2主要用于核技术,作为核反应堆,特别是水堆(BWRs)燃料棒的包层。因此锆合金的高强度是至关重要的。通过对锆合金拉伸性能的比较,研究了低温轧制对锆合金拉伸性能的影响。为了进行分析,取了4个不同程度的冷轧试样,并对这些试样进行了拉伸试验。对所得结果进行了分析,得出了锆合金-2的最佳冷滚度。由于位错在晶界附近的缠结和晶粒尺寸的减小,低温轧制改善了材料的力学性能。用光学显微镜分析了样品的显微组织、冷轧前后的显微组织,并进行了晶粒组织分析。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Tensile Behavior of Cryorolled Zircaloy-2
Zircaloy-2 is mainly used in nuclear technology, as cladding of fuel rods in nuclear reactors, especially water reactors (BWRs). Hence high strength of Zirca loy-2 is of prime importance. This investigation deals with the effect of cryorolling on Zircaloy-2 by co mparing d ifferent tensile properties. For this analysis, four samp les with various degrees of cryorolling are taken and tensile tests are conducted on these samples. The obtained results are analyzed and the optimu m degree of cryorolling of Zircaloy-2 is obtained. The cryorolling imp roved the mechanical properties of the material as the dislocations are entangled near the grain boundaries and also due to decrease in the grain size. The microstructure of the sample is analysed by optical microscope, before and after cryorolling and the grain structure analysis is done.
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