Citation: | Luo Juan, Qi Min, Tang Peng, Tang Long, Yao Di. Experimental Investigation on Fatigue Crack Propagation Behavior of Nuclear Pipe at High Temperature[J]. Nuclear Power Engineering, 2022, 43(S1): 142-145. doi: 10.13832/j.jnpe.2022.S1.0142 |
[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.
|