[1] | Cao Yuming, Zhao Gang, Fang Zheng, Li Yuhuan, Zhou Du, Liu Wenshi, Wang Zheng. Study on Calculation Method of Crack Leakage Rate of Valve Sealing Surface[J]. Nuclear Power Engineering, 2025, 46(1): 136-142. doi: 10.13832/j.jnpe.2025.01.0136 |
[2] | Zhang Wei, Li Jingsong, Shi Huilie, Qiao Pengrui, Wang Cong, Zhang Tianqing, He Yingzhao. Thermal-Hydraulic Performance Analysis of Horizontal Spiral Tube Steam Generator for European Lead-Cooled Fast Reactor[J]. Nuclear Power Engineering, 2022, 43(3): 38-45. doi: 10.13832/j.jnpe.2022.03.0038 |
[3] | Li Yilei, Li Pengzhou, Yao Di, Qiao Hongwei, Zhang Kun, Sun Lei. Study on Crack Impact Toughness Evaluation Method for Metallic Materials[J]. Nuclear Power Engineering, 2021, 42(5): 114-118. doi: 10.13832/j.jnpe.2021.05.0114 |
[4] | Liu Hao, Ma Zaiyong, Jiang Zhangrui, Tang Yu, Zhang Luteng, Xu Jianjun, Sun Wan, Yuan Dewen, Pan Liangming, Zhou Wenxiong. Simplification of Critical Criteria for Reverse Flow Determination Based on Reverse Flow Theory Model of U-Tube Steam Generator[J]. Nuclear Power Engineering, 2021, 42(6): 77-81. doi: 10.13832/j.jnpe.2021.06.0077 |
[5] | Zhao Pengcheng, Yi Feng, Yu Hongxing, Shi Wei, Wang Tianshi, Xia Bangyang, Chen Baowen. Research on Flow Distribution Characteristics of Inverted U- Shaped Tube of Steam Generator under Natural Circulation Condition[J]. Nuclear Power Engineering, 2021, 42(1): 192-197. doi: 10.13832/j.jnpe.2021.01.0192 |
[6] | Peng Yanhua, Zhu Wei, Wen Bang, Yang Fan, Fan Shen, Meng Zhiliang, Jiang Linzhi. Study on Post-Irradiation Microstructure of UO2 Pellets in Recycled Uranium Fuel Elements[J]. Nuclear Power Engineering, 2019, 40(2): 27-31. doi: 10.13832/j.jnpe.2019.02.0027 |
[7] | Tan Wei, Jiang Songyuan, Xiong Guangming, Jia Zhanbin, Guo Kai. Sensitivity Analysis of Effect of Anti-Vibration Bar Gap on Natural Frequency of U Tube in Steam Generators[J]. Nuclear Power Engineering, 2019, 40(2): 53-57. doi: 10.13832/j.jnpe.2019.02.0053 |
[8] | Zhao Guobin, Hu Anzhong, Bie Chao, Jiang Shujie. Improvement of Ultrasonic Testing Process for Bottom Seal Head and Pipe Plate Circumferential Weld of Steam Generator in EPR Project[J]. Nuclear Power Engineering, 2019, 40(2): 137-140. doi: 10.13832/j.jnpe.2019.02.0137 |
[9] | Xin Sufang, Li Songyu, Ren Chunming, Wang Wei, Xiao Peng. Study on a CFD Simplified Approach for Steam Generator U-Tube[J]. Nuclear Power Engineering, 2018, 39(S1): 41-44. doi: 10.13832/j.jnpe.2018.S1.0041 |
[10] | Tan Guowei, Zhang Minjie, Deng Feng. Research of Lattice Style Tube Support Sheet Used by Steam Generator[J]. Nuclear Power Engineering, 2016, 37(S1): 34-37. doi: 10.13832/j.jnpe.2016.S1.0034 |
[11] | Li Yong, Zhu Haiyan, Wen Bo, Zhao Erlei, Zan Yuanfeng, Zhuo Wenbin, Li Pengzhou. Scale Analysis of Hydraulic Test of Tube Support Plate in Steam Generator Based on Computational Fluid Dynamics[J]. Nuclear Power Engineering, 2016, 37(4): 39-43. doi: 10.13832/j.jnpe.2016.04.0039 |
[12] | Wen Bo, Li Yong, Xiong Ting, Zan Yuanfeng, Yan Xiao, Zhuo Wenbin, Li Pengzhou. Experimental Study on Hydraulic Characteristics of Tube Support Plate in Steam Generator[J]. Nuclear Power Engineering, 2016, 37(2): 23-26. doi: 10.13832/j.jnpe.2016.02.0023 |
[13] | Pan Keqi, Zhang Xu. Theory and Simulation Investigation on Crack Tip Blunting for Ductile Material[J]. Nuclear Power Engineering, 2015, 36(5): 128-131. doi: 10.13832/j.jnpe.2015.05.0128 |
[14] | Zhang Tianyi, Zhang Zhenxing, hu Lina, Xu Yu. Effect of Tube Structural Style on Thermal Stress in CEFR Intermediate Heat Exchanger[J]. Nuclear Power Engineering, 2015, 36(5): 148-151. doi: 10.13832/j.jnpe.2015.05.0148 |
[15] | Ni Peng, Hui Hu, Wang Xiaodong, Lin Shaoxuan, Zhang Liyan, Chen Qingqi. Numerical Simulation of Hydraulically Expanded Tube-to-Tube Sheet Joints in Steam Generator[J]. Nuclear Power Engineering, 2015, 36(5): 204-207. doi: 10.13832/j.jnpe.2015.05.0204 |
[16] | REN Hongbing, XIE Honghu, ZHOU Peng. Design Improvement of CPR1000 Steam Generator Supports[J]. Nuclear Power Engineering, 2014, 35(2): 131-133. |
[17] | XiN Sufang, Peng Shinian, Zhang Yu. Study on Reverse Flow in U-Tube Steam Generator under Natural Circulations[J]. Nuclear Power Engineering, 2014, 35(3): 11-14. doi: 10.13832/j.jnpe.2014.03.0011 |
[18] | Du Nanlin, Chen Zhongzhuo, Chen Fubin. Disposition of Drilling Deviation for Steam Generator Tubesheet in Sanmen NPP Unit 2[J]. Nuclear Power Engineering, 2014, 35(3): 76-79. doi: 10.13832/j.jnpe.2014.03.0076 |
[19] | WANG Meng, WANG Jianjun, SUN Zhongning, HE Shijing, YAN Changqi. Optimum Design of Steam Generator[J]. Nuclear Power Engineering, 2011, 32(1): 29-33. |
[20] | CAI Fengchun, ZANG Fenggang, YE Xianhui. Stability of Cracked Cantilevered Pipes Conveying Fluid[J]. Nuclear Power Engineering, 2011, 32(3): 116-121. |