[1] | Huang Zhe, Liang Tiebo, Yang Wen, Lu Chuan, Li Yang, He Zhonghai, Shen Xin. Analysis of Steady and Transient Characteristics of Once-through Steam Generator for Lead Bismuth Fast Reactor[J]. Nuclear Power Engineering, 2024, 45(2): 103-109. doi: 10.13832/j.jnpe.2024.02.0103 |
[2] | Li Tian, Xue Donglin, Chen Yanhui, Shao Chunbing, Huang Song, Hui Hu, Jiao Peng. Study on Limitation Size of Fretting Wear of Inconel 690 Steam Generator Tube[J]. Nuclear Power Engineering, 2024, 45(6): 147-152. doi: 10.13832/j.jnpe.2024.06.0147 |
[3] | Du Daiquan, Zhang Ting, Zhuo Wenbin. Experimental Study on the Influence of Thermal Parameter Deviation on Steady-state Characteristic of Once-through Steam Generator[J]. Nuclear Power Engineering, 2024, 45(6): 84-90. doi: 10.13832/j.jnpe.2024.06.0084 |
[4] | Chen Ling, Wang Xinming, Zhang Yongfa, Zhang Liming, Jiang Lizhi, Jiao Meng, Liu Xiaoya. Analysis of Thermal Stress and Fatigue Induced by Dryout Oscillation in Once Through Steam Generator[J]. Nuclear Power Engineering, 2023, 44(4): 121-127. doi: 10.13832/j.jnpe.2023.04.0121 |
[5] | 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 |
[6] | He Feng, Zhu Jianping, Lu Yuechuan, Lu Xifeng, Wang Xinjun, Li Xiao. Quantitative Study on 5% Damage Rate of Steam Generator Heat Transfer Tube in M310 Unit[J]. Nuclear Power Engineering, 2022, 43(4): 191-195. doi: 10.13832/j.jnpe.2022.04.0191 |
[7] | Xu Yu, Huangfu Zeyu, Xu Jianqun, Tian Peiyu, Li Chunmei, Cheng Xiang, Yan Siwei, Liao Xianwei. Simulation Research on Dynamic Characteristics and Small Break Fault of Once-through Steam Generator[J]. Nuclear Power Engineering, 2021, 42(2): 161-167. doi: 10.13832/j.jnpe.2021.02.0161 |
[8] | He Gening, Li Xiaojia, Cong Tenglong, Chen Yiran, Li Donghui, Wu Ge. Investigation on Reversed Flow Characteristics of U-Tube Steam Generator under Ocean Conditions[J]. Nuclear Power Engineering, 2021, 42(3): 37-42. doi: 10.13832/j.jnpe.2021.03.0037 |
[9] | Ding Xueyou, Chen Zhiqiang, Wen Qinglong, Ruan Shenhui, Qiao Pengrui. Numerical Investigation on Thermal Hydraulics of Helical Coil Tube Once Through Steam Generator for LBE Fast Reactor[J]. Nuclear Power Engineering, 2021, 42(4): 21-26. doi: 10.13832/j.jnpe.2021.04.0021 |
[10] | Zhao Xiao, Bai Yufei, Zhang Zhen, Yang Xingtuan. Numerical Simulation of Steady-State and Transient Characteristics of Once Through Steam Generators[J]. Nuclear Power Engineering, 2020, 41(6): 8-13. |
[11] | Development and Application of Eddy Current Inspection System for Heat-Exchanging Tubes of Horizontal Steam Generator[J]. Nuclear Power Engineering, 2019, 40(3): 150-154. doi: 10.13832/j.jnpe.2019.03.0150 |
[12] | Liu Yun, Lu Wei, Ding Song, Yin Peng, Yang Jinli. Immersion Ultrasonic Inspection for Expanding Area of Steam Generator Tubes[J]. Nuclear Power Engineering, 2018, 39(4): 75-79. doi: 10.13832/j.jnpe.2018.04.0075 |
[13] | Tian Xiaoyan, Jiang Xinbiao, Chen Lixin, Li Huaqi, Yang Ning, Zhu Lei, MA Tengyue. Development of Code for Steady-State Thermal-Hydraulic Analysis in Bimodal Space Nuclear Reactor with Heat Pipe[J]. Nuclear Power Engineering, 2017, 38(5): 34-39. doi: 10.13832/j.jnpe.2017.05.0034 |
[14] | Lin Zhenxia, Dang Ying, Xu Qi, Chen Yong. Research on Intergranular Corrosion of Alloy 690 Used in SG Tubes[J]. Nuclear Power Engineering, 2017, 38(S2): 128-130. doi: 10.13832/j.jnpe.2017.S2.0128 |
[15] | Li Pengfei, Yu Ping, Wang Haisong, Cheng Xiang, Li Huanming, Huang Wei, Shen Yunhai. Study on Design Improvements of Recirculation SG Based on Ageing Degradations[J]. Nuclear Power Engineering, 2016, 37(5): 115-118. doi: 10.13832/j.jnpe.2016.05.0115 |
[16] | Gao Lixia, Yu Danping, Tan Tiancai, Ma Jianzhong, Liu Litao. Study on Dynamic Characteristics of Heat Transfer Tube in SG[J]. Nuclear Power Engineering, 2015, 36(5): 65-67. doi: 10.13832/j.jnpe.2015.05.0065 |
[17] | Shi Shaobo, Shen Ping, Tian Xianglu, Gao Luyang. Validity Analysis of Rolled Plugs of Steam Generators Tube[J]. Nuclear Power Engineering, 2015, 36(5): 72-74. doi: 10.13832/j.jnpe.2015.05.0072 |
[18] | Zhu Yong, Qin Jiaming, ReN Hongbing, Zuo Chaoping, Han Tongxing. Flow-Induced Vibration Analysis of Steam Generator Heat Transfer Tube Based on ANSYS[J]. Nuclear Power Engineering, 2014, 35(4): 17-20. doi: 10.13832/j.jnpe.2014.04.0017 |
[19] | CHEN Zhi, LIAO Longtao, LIU Lixin, LI Wei. Study on Application of T-S Fuzzy Neural Method in Once Through Steam Generator Feedwater Control[J]. Nuclear Power Engineering, 2012, 33(4): 20-23,33. |
[20] | WEI Xin-yu, DAI Chun-hui, ZHAO Fu-yu. Heat Transfer Optimization of Once-Through Steam Generator[J]. Nuclear Power Engineering, 2011, 32(6): 119-124. |