Experimental Investigation on Fatigue Crack Propagation Behavior of Nuclear Pipe at High Temperature
-
摘要: 为研究核级管道材料在500℃以上的高温疲劳裂纹扩展性能,对管道母材、焊缝和热影响区材料进行了高温条件下的疲劳裂纹扩展速率试验,基于概率分析方法获得了考虑不同存活率的概率疲劳裂纹扩展曲线。研究结果表明,高温条件下,管道不同位置区域材料的疲劳裂纹扩展性能存在较为明显的差异,焊缝和热影响区的抗疲劳裂纹扩展能力明显优于母材。试验研究结果可用于核反应堆管道结构安全评估和断裂力学分析。Abstract: In order to study the fatigue crack growth performance of nuclear piping materials at elevated temperature above 500℃, the fatigue crack propagation rate experiments on the materials of base metal, welded seam and heat affected zone of tube were carried out under high temperature conditions. The probabilistic fatigue crack growth curves with different survival rates were obtained according to the method of probability analysis. The results show that there are obvious differences in fatigue crack growth performance of materials in different positions of pipelines at high temperature, and the resistance of fatigue crack propagation for welded seam and heat-affected zone is much better than that of base metal. The results can be used for safety assessment and fracture mechanics analysis of nuclear reactor pipeline structure.
-
Key words:
- Nuclear pipe /
- High temperature /
- Fatigue crack propagation /
- Probability
-
表 1 试验工况
Table 1. Test Conditions
取样位置 B /mm R 试样数量/件 T/℃ 母材 10 0.1 15 580 母材 10 0.5 3 580 母材 10 0.1 4 505 母材 5 0.1 5 580 焊缝 5 0.1 5 580 热影响区 5 0.1 5 580 -
[1] FISHER A. 新型核反应堆[J]. 严小平,译. 世界科学,1997(9): 31-34. [2] 朱继洲. 核反应堆安全分析[M]. 西安: 西安交通大学出版社, 2004. [3] 杨冰,赵永翔,何朝明,等. 考虑概率与置信度的疲劳裂纹扩展率模型及其参数测定方法[J]. 机械工程学报,2004, 40(6): 183-187. doi: 10.3321/j.issn:0577-6686.2004.06.036 [4] ASTM. Standard test method for measurement of fatigue crack growth rates: ASTM E647[S]. West Conshohocken: ASTM, 2008.