氢化CZ2合金疲劳性能研究

IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY
Jieming Huang, Changyuan Gao, Liu-tao Chen, Xu Wang, J. Tan
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引用次数: 0

摘要

CZ2合金是中国核电技术研究院自主研发的具有自主知识产权的新型Zr-Nb锆合金。在反应堆使用过程中,锆会与冷却剂发生反应,吸收氢,从而降低锆合金的性能,导致失效。因此,在许多锆合金性能的研究中,经常使用氢化来模拟燃耗。本文采用气充氢法制备了含氢量为400ppm左右的CZ2合金。将试样在加氢环境中加温至500℃,保温1.5 h,在343℃下进行了非对称轴向拉拉加载下的氢化/非氢化CZ2合金和非氢化Zr-4合金的疲劳试验,研究了氢化物对CZ2合金疲劳性能的影响。结果表明:随着应力水平的降低,未氢化的CZ2合金与氢化的疲劳寿命差异越来越大,且未氢化的CZ2合金的疲劳寿命高于氢化的;未氢化的CZ2合金的疲劳性能优于Zr-4合金。采用两参数模型和三参数模型对CZ2合金的疲劳数据进行拟合。结果表明,三参数模型能较好地描述CZ2合金的疲劳寿命。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Study on Fatigue Properties of Hydrided CZ2 Alloy
CZ2 alloy is a new Zr-Nb zirconium alloy independently developed by China Nuclear Power Research and Technology Institute (CNPRI), which has independent intellectual property rights. Zirconium will react with coolant to absorb hydrogen in reactor service, which will degrade the performance of zirconium alloy and lead to failure. Therefore, in many studies of zirconium alloy performance, hydriding is often used to simulate burnup. In this paper, CZ2 alloy with hydrogen content of about 400 ppm was obtained by gaseous hydrogen charging method. The sample was heated to 500°C with the furnace in hydrogen environment and kept for 1.5 h. Then the fatigue tests of hydrided/un-hydrided CZ2 alloy and un-hydrided Zr-4 alloy under asymmetric axial pull-pull loading at 343°C were carried out to study the effect of hydride on the fatigue properties of CZ2 alloy. The results show that with the decrease of stress level, the difference between the fatigue life of CZ2 alloy un-hydrided and that of hydrided becomes larger, and the fatigue life of CZ2 alloy un-hydrided is higher than that of hydrided. The fatigue properties of un-hydrided CZ2 alloys are better than Zr-4 alloys. The two-parameter model and three-parameter model are used to fit the fatigue data of CZ2 alloy. It is found that the three-parameter model can better describe the fatigue life of CZ2 alloy.
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来源期刊
CiteScore
0.80
自引率
25.00%
发文量
35
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