[1] | Liu Yang, Lu Zhiwei, Ge Hongen, Wu Lixiang, Xue Jiaxiang, Liao Yehong. Study on Internal Pressure Burst, Creep and Fatigue Properties of ODS-FeCrAl Alloy Tube[J]. Nuclear Power Engineering, 2024, 45(S1): 145-151. doi: 10.13832/j.jnpe.2024.S1.0145 |
[2] | 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 |
[3] | Shi Kaikai, Zheng Bin, Zheng Liangang. Simulation Study on Fatigue Growth of Semi-Circular Axial Crack on Inner Surface of Core Barrel under Transient Loads[J]. Nuclear Power Engineering, 2021, 42(S2): 1-4. doi: 10.13832/j.jnpe.2021.S2.0001 |
[4] | Chen Liang, Song Xiaoming, Pang Hua, Wang Kecheng, Huo Meng, Zeng Xiangguo. Calculation of Stress Intensity Factor of Zr-4 Cladding Tube by Flexibility Method[J]. Nuclear Power Engineering, 2019, 40(5): 202-206. |
[5] | Du Donghai, Chen Kai, Zhang Lefu, Shi Xiuqiang, YiN Kaiju. Effect of Zinc on Stress Corrosion Crack Growth Rate of Type 316 Stainless Steel[J]. Nuclear Power Engineering, 2017, 38(2): 78-83. doi: 10.13832/j.jnpe.2017.02.0078 |
[6] | Dai Xun, Wang Pengfei, Wang Ying, Cheng Zhuqing, Yang Zhongbo, Zhao Wenjin, Zhuo Hong. Study on Second Phase Particles in N36 Alloy Claddings and Bars[J]. Nuclear Power Engineering, 2017, 38(S1): 13-17. doi: 10.13832/j.jnpe.2017.S1.0013 |
[7] | Luo Jiacheng, Zhang Yong, Li Pengzhou, Luo Juan, Sun Lei. Crack Growth Analysis of Ω Seal Overlay Weld Repair for CRDM[J]. Nuclear Power Engineering, 2016, 37(S2): 11-13. doi: 10.13832/j.jnpe.2016.S2.0011 |
[8] | ZHENG Liangang, XIE Hai, SU Dongchuan, SHAO Xuejiao. Study of Reactor Pressure Vessel Fatigue Crack Growth Analysis Based on ANSYS[J]. Nuclear Power Engineering, 2015, 36(6): 67-69. doi: 10.13832/j.jnpe.2015.06.0067 |
[9] | Xiao Jun, Chen Luyao, Fu Zhenghong, Qiu Shaoyu, Chen Yong, Lin Zhenxia. Corrosion Fatigue Cracking Behavior of Inconel 690(TT) in Secondary Water of Pressurized Water Reactors[J]. Nuclear Power Engineering, 2015, 36(4): 83-85. doi: 10.13832/j.jnpe.2015.04.0083 |
[10] | YAN Meng, WANG Pengfei, LIANG Bo, HONG Xiaofeng. Iodine Induced Stress Corrosion Cracking of N36 Zirconium Tube in Hoop Tensile Condition[J]. Nuclear Power Engineering, 2015, 36(1): 46-49. doi: 10.13832/j.jnpe.2015.01.0046 |
[11] | XIAO Jun, CHEN Luyao, FU Zhenghong, QIU Shaoyu, CHEN Yong, LIN Zhenxia. Corrosion Fatigue Cracking of Inconel 690(TT) with Crack-tip Area under Small Scale Yielding[J]. Nuclear Power Engineering, 2015, 36(1): 41-45. doi: 10.13832/j.jnpe.2015.01.0041 |
[12] | Du Donghai, Zhang Lefu, Chen Kai, Yu Lun, Shi Xiuqiang, Xu Xuelian. Measurement of Crack Growth Rate of Alloy X-750 Based on DCPD Method[J]. Nuclear Power Engineering, 2014, 35(4): 163-167. doi: 10.13832/j.jnpe.2014.04.0163 |
[13] | MAO Xue-ping, GUO Qi, ZHANG Sheng-yuan, HU Su-yang, LU Dao-gang, XU Hong. Study on Creep Damage Behaviors of Ni-Based Alloy C276[J]. Nuclear Power Engineering, 2013, 34(2): 86-89. |
[14] | ZHENG Zhangli, WU Zhiyuan, CAO Ding. Analysis of Cold Crack of AP1000 Steam Generator Tube Sheet Cladding[J]. Nuclear Power Engineering, 2012, 33(5): 120-123. |
[15] | DAI Xun, LIU Hong, WANG Pengfei, WANG Ying, ZHAO Wenjin. Study on Microstructure and Texture of Processed N18 Plates by EBSD[J]. Nuclear Power Engineering, 2012, 33(S2): 17-21. |
[16] | YAN Meng, PENG Qian, WANG Pengfei, ZHAO Wenjin. Research on Hoop Tensile Test Method for N36 Zirconium Tube[J]. Nuclear Power Engineering, 2012, 33(S2): 13-16. |
[17] | YAN Meng, PENG Qian, ZHAO Wenjin, SHENG Zhongqi, DAI Xun. Fracture Morphology Analysis of Iodine Induced Stress Corrosion Cracking of N36 Zirconium Tube[J]. Nuclear Power Engineering, 2012, 33(S2): 47-50. |
[18] | DAI Xun, LIU Hong, WANG Pengfei, WANG Ying, ZHAO Wenjin, SHI Minghua. Study on Microstructure of Hot Extruded N36 Zirconium Alloy Tubes[J]. Nuclear Power Engineering, 2012, 33(S2): 43-46,78. |
[19] | LI Qiang, HUANG Changjun, YANG Yanping, XU Long, LIANG Xue, ZHOU Bangxin. Nodular Corrosion Investigation of N18 Zirconium Alloys[J]. Nuclear Power Engineering, 2012, 33(S2): 22-27,38. |
[20] | WANG Pengfei, ZHAO Wenjin, YAN Meng. Review of Investigations on Anisotropic Creep Behavior of Zr Alloy Cladding[J]. Nuclear Power Engineering, 2012, 33(S2): 28-34. |