[1] | Yue Huifang, Pang Hua, Gao Bo, Gao Shixin, Luo Qianqian, Zhao Yanli, Jiang Yourong. Effect of Fe+Cr and Si Contents on Corrosion Resistance of Zircaloy-4[J]. Nuclear Power Engineering, 2024, 45(3): 146-153. doi: 10.13832/j.jnpe.2024.03.0146 |
[2] | Zhuo Weiqian. Research on U-Zr-based Metallic Fuel Additives and Performance Improvement for Fuel-Cladding Chemical Interaction and Phase Optimization[J]. Nuclear Power Engineering, 2023, 44(S1): 158-162. doi: 10.13832/j.jnpe.2023.S1.0158 |
[3] | Yan Meng, Li Shunping, Wang Pengfei, Hong Xiaofeng, Liang Bo, Dai Xun, Yin Qiwei. Research on Hoop Mechanical Property of Zr-Sn-Nb Alloy Cladding Tubes in Vacuum[J]. Nuclear Power Engineering, 2023, 44(3): 127-131. doi: 10.13832/j.jnpe.2023.03.0127 |
[4] | Yu Hang, Zhao Xinwen, Fu Shengwei, Zhu Kang. Structural Integrity Analysis of Fuel Element Cladding Based on Fluid-Solid-Heat Coupling[J]. Nuclear Power Engineering, 2022, 43(4): 106-112. doi: 10.13832/j.jnpe.2022.04.0106 |
[5] | Zhang Ruikai, Liu Pan, Tan Jianping, Li Yue, Wang Dasheng, Tu Shandong. Calculation of Stress Intensity Factor of External Surface Crack on the Nozzle of Steam Generator in Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(5): 138-146. doi: 10.13832/j.jnpe.2022.05.0138 |
[6] | Zhu Bida, Shi Kaikai, Zheng Bin. Calculation of Stress Intensity Factor for Surface Cracks in FeCrAl Cladding under Force-Irradiation Coupling[J]. Nuclear Power Engineering, 2022, 43(S2): 177-181. doi: 10.13832/j.jnpe.2022.S2.0177 |
[7] | Li Chenyue, Dong Bing, Yin Junlian, Li Leihao, Wang Dezhong. Computational Simulation Research of Unstable Mechanics of Fission Gas Release under Condition of Fuel Cladding Breach[J]. Nuclear Power Engineering, 2020, 41(3): 97-103. doi: 10.13832/j.jnpe.2020.03.0097 |
[8] | Chen Boquan, Peng Qian, Zeng Zihan, Zhao Suqiong, Hong Xiaofeng, Qiu Shaoyu, Xu Chunrong. Research on Preparation Method for Zr-4 Tubes with Different Hydride Orientation[J]. Nuclear Power Engineering, 2019, 40(1): 51-55. doi: 10.13832/j.jnpe.2019.01.0051 |
[9] | Chen Boquan, Peng Qian, Hong Xiaofeng, Liu Ranchao, Qiu Shaoyu, Xie Huaiying, Chen Le. Effect of Hydride Orientation on Tensile and Bursting Properties of Zr-4 Cladding Tubes at Room Temperature[J]. Nuclear Power Engineering, 2019, 40(1): 60-64. doi: 10.13832/j.jnpe.2019.01.0060 |
[10] | Wang Zhen, ZHou Bangxin, Zhu Wei, Wen Bang, Tang Hongkui, Fang Zhongqiang. In-situ Heating Investigation on Lattice Evolution of Zircaloy-4 during Its Oxidation Process[J]. Nuclear Power Engineering, 2017, 38(S1): 140-144. doi: 10.13832/j.jnpe.2017.S1.0140 |
[11] | Xia Jianwen, Han Cheng. Ultrasonic Inspection for Zirconium Alloy Nuclear Fuel Cladding Tubes[J]. Nuclear Power Engineering, 2016, 37(3): 122-126. doi: 10.13832/j.jnpe.2016.03.0122 |
[12] | 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 |
[13] | LI Yuanming, XIE Qingqing, XIN Yong, ZHOU Yi. Cladding Surface Temperature Limit for Fuel Element Aluminum-Alloy Cladding of Research and Test Reactors[J]. Nuclear Power Engineering, 2015, 36(6): 154-157. doi: 10.13832/j.jnpe.2015.06.0154 |
[14] | Wang Dasheng, Liu Pan, Xiong Guangming. Fracture Mechanics Analysis for Inlet Nozzle of RPV with Pipe Load Considered[J]. Nuclear Power Engineering, 2015, 36(5): 120-123. doi: 10.13832/j.jnpe.2015.05.0120 |
[15] | 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. |
[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] | FU Yuanjie, ZHANG Haisheng, HUANG Juan, LI Furong, CUI Yonghai, SUN Kai. Vickers Micro-Hardness Analysis of Irradiated Zr-2 Alloy Tube[J]. Nuclear Power Engineering, 2012, 33(S2): 35-38. |
[18] | 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. |
[19] | ZHENG Bin, ZANG Fenggang, SUN Yingxue. Pressurized Thermal Shock Analysis for Reactor Pressure Vessels[J]. Nuclear Power Engineering, 2012, 33(1): 1-3,13. |
[20] | LIU Jun, YAN Bo, LU Yuechuan, SUN Yingxue, JIANG Naibin, CHANG Xueping. Fracture Analysis for Pressure Pipe Wrapped with Carbon-Fiber Reinforced Composites[J]. Nuclear Power Engineering, 2011, 32(2): 48-52,115. |