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热处理后Zr-4合金高温氧化行为研究 被引量:2

High-Temperature Oxidation Behavior of Heat Treated Zr-4 Alloy
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摘要 为了了解马氏体态Zr-4合金的高温氧化性能,以热处理后马氏体态的Zr-4合金为研究对象,利用热分析天平,采用动态连续称重法对Zr-4合金分别在450℃水蒸气、500℃水蒸气和500℃空气条件下进行氧化试验,对其氧化动力学规律进行了分析,利用扫描电子显微镜和能谱分析仪对氧化层的形貌和成分进行了观察分析.试验结果表明:Zr-4合金在450℃水蒸汽、500℃的水蒸气和500℃空气条件下的氧化动力学符合抛物线规律y=a+btc,随着氧化时间的延长,氧化速度减慢;氧化温度升高,氧化速度增快.在氧化220h后会形成厚度均匀的氧化膜,厚度分别为10.8μm、35μm和47.7μm;氧化膜表面有部分破裂和脱落;氧化膜主要含Zr和O元素,从氧化膜外表面到基体,O元素含量逐渐降低,Zr元素含量逐渐增加. In order to understand high-temperature oxidation behavior of martensitic Zr-4 alloy, the oxidation dynamic rules of Zr-4 alloys at 450 ℃ vapor, 500 ℃ vapor and 500 ℃ air were analyzed by dynamic continuous weighing methods. The microstructures and compositions of the oxide layers were observed by SEM and EDS. The results showed. Oxidation dynamics of Zr-4 alloys at 450 ℃ vapor, 500 ℃ vapor and 500 ℃ air conditions were in line with parabolic rules. The oxidation speeds decreased with the extension of oxidation time,and the oxidation rates increased with increasing temperature. After Zr-4 alloy oxidized at 450 ℃ vapor,500 ℃ vapor and 500 ℃ air conditions for 220 h,the oxide layer thickness were respectively 10.8 μm,35 μm and 47.7 μm,and oxidation layers became broken and peeling off. Zr and O contents in the layers individually increased and decreased with distance from surface to substrate.
出处 《西安工业大学学报》 CAS 2015年第4期329-334,共6页 Journal of Xi’an Technological University
基金 国家大学生创新创业项目(201310702018)
关键词 ZR-4合金 高温氧化 高温水蒸气 氧化动力学 Zr-4 alloy high-temperature oxidation high-temperature steam oxidation dynamic
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  • 1王剑钊,苗廼金,王保民,卢刚.核电技术的发展动态[J].热力发电,2004,32(12):1-4. 被引量:2
  • 2张长义,宁广胜,佟振峰,林虎,徐远超.M5锆合金包壳管轴向和环向拉伸性能测试[J].原子能科学技术,2005,39(B07):34-36. 被引量:10
  • 3雷鸣,刘文庆,严青松,李强,姚美意,周邦新.变形及热处理对Zr-Sn-Nb新锆合金第二相粒子的影响[J].稀有金属材料与工程,2007,36(3):467-470. 被引量:16
  • 4Steinberg E, Weidinger H G, Schaa A. Zirconium in the Nuclear Industry : Sixth International Symposium [ C ]. ASTM-STP-824, 1984 : 106 - 122.
  • 5Foster J P, Dougherty J, Burke M G, et al. Influence of final recrystallization heat treatment on Zircaloy-4 strip corrosion [ J ]. J. Nucl. Mat, 1990, 173(2):146-178.
  • 6Li C,Zhou B X, Zhao W J, et al. Determination of Fe and Cr content in α-Zr solid solution of Zircaloy-4 with different heat-treated states[ J]. J. Nucl. Mat, 2002 : 134 - 138.
  • 7姚美意,周邦新,李强,刘文庆,虞伟均,褚于良.热处理对Zr-4合金在360℃ LiOH水溶液中腐蚀行为的影响[J].稀有金属材料与工程,2007,36(11):1920-1923. 被引量:15
  • 8阎昌琪.核反应堆工程[M]哈尔滨:哈尔滨工程大学出版社,2004.
  • 9STEINBERG E,WEIDINGER H G,SCHAA A. Analytical Approachs and Experimental verification to Describe the Influence of Cold Work and Heat Treatment on the Mechanical Properties of Zircaloy Cladding Tube[A].Philadelphia:American Society for Testing and Materials,1984.106.
  • 10赵文金.我国高性能锆合金的发展及应用前景[R]成都:中国核动力研究设计院,2000.

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