[1] | Liu Yong, Duan Tianying, Feng Weiwei, Zhang Weiying. Design and Experiment of Feed-water Control System for CEFR Steam Generator[J]. Nuclear Power Engineering, 2024, 45(2): 183-186. doi: 10.13832/j.jnpe.2024.02.0183 |
[2] | Huang Jun, Ying Bingbin, Zheng Mingguang. Flow Field and Blowdown Test of Secondary Side Lower Part of Steam Generator[J]. Nuclear Power Engineering, 2024, 45(2): 193-198. doi: 10.13832/j.jnpe.2024.02.0193 |
[3] | Zhang Jibin, Lyu Huanwen. Experimental Research on Effect of Aerosol in Liquid Pool on Size of Bubbles from Submerged Orifice[J]. Nuclear Power Engineering, 2021, 42(5): 245-249. doi: 10.13832/j.jnpe.2021.05.0245 |
[4] | Wang Xiaoming, Yang Hongwei. Design of a Ventilation Flow Orifice Plate Aperture Regulator[J]. Nuclear Power Engineering, 2019, 40(6): 168-172. doi: 10.13832/j.jnpe.2019.06.0168 |
[5] | Mu Guanyu. Experimental Study on Design and Layout of Recirculation Valve for Main Feedwater System of Nuclear Power Plants[J]. Nuclear Power Engineering, 2019, 40(6): 155-158. doi: 10.13832/j.jnpe.2019.06.0155 |
[6] | Liang Congcong, Song Mingliang, Zeng Xiaokang. Cause Analysis and Treatment of Pipeline Vibration of Check Valve in Fuqing Nuclear Power Plant[J]. Nuclear Power Engineering, 2018, 39(S2): 154-156. doi: 10.13832/j.jnpe.2018.S2.0154 |
[7] | Zhao Jiaming, Wang Guangfei, Zhu Dahuan, Zhao Bin. Optimization Study of Improving Cavity Injection and Cooling System Performance[J]. Nuclear Power Engineering, 2018, 39(S1): 102-105. doi: 10.13832/j.jnpe.2018.S1.0102 |
[8] | Zhang Yulong, Li Yanglong. Analysis and Design of Solved Method on Main Feed Water Regulating Valve Frequent Fault of Qinshan 2th Nuclear Power Plant[J]. Nuclear Power Engineering, 2017, 38(6): 117-121. doi: 10.13832/j.jnpe.2017.06.0117 |
[9] | 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 |
[10] | 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 |
[11] | He Chao, Lai Jiang, Yan Junming, Xi Zhide, Yuan Shaobo, Sun Lei. Research on Vibration Issue due to Pipe Orifice Cavitation[J]. Nuclear Power Engineering, 2016, 37(S2): 65-69. doi: 10.13832/j.jnpe.2016.S2.0065 |
[12] | Liu Qiang, Zhang Xiaoguang. Analysis of Thread Corrosion Damage in Primary Manway of Steam Generator and Application of Thread Wire[J]. Nuclear Power Engineering, 2015, 36(S1): 82-84. doi: 10.13832/j.jnpe.2015.S1.0082 |
[13] | Tian Haowen, Zhang Tengfei, Ceng Xiaokang. Mechanism Analysis and Improvement Measures for ThicknessReducing of Pipe behind Restriction Orifice in Deaerating System in Nuclear Power Plants[J]. Nuclear Power Engineering, 2015, 36(S1): 194-197. doi: 10.13832/j.jnpe.2015.S1.0194 |
[14] | Zhao Jingxiong, Liu Zhangliang. Analysis and Improvement of Throttling Orifice of NPP RCV System[J]. Nuclear Power Engineering, 2015, 36(4): 28-31. doi: 10.13832/j.jnpe.2015.04.0028 |
[15] | Wang Changzheng. Commissioning of Main Feed Water Control Valves after Replacement[J]. Nuclear Power Engineering, 2015, 36(S1): 114-117. doi: 10.13832/j.jnpe.2015.S1.0114 |
[16] | Li Heng. Study on Commission of Equipment Cooling Water System in Nuclear Power Plants[J]. Nuclear Power Engineering, 2015, 36(S1): 166-169. doi: 10.13832/j.jnpe.2015.S1.0166 |
[17] | Zeng Chang, Lai Jianyong, Duan Yongqiang. Analysis and Improvement of Auxiliary Feedwater System Excessive Flow Based on 1D-3D Models[J]. Nuclear Power Engineering, 2014, 35(S1): 93-96. |
[18] | ZHAO Xin, TAN Haibo, LIU Bo, WANG Jianghong, ZHAI Bajing. Research on Dimension Calculation of CPR1000 Safety Injection System High-pressure Restriction Orifices[J]. Nuclear Power Engineering, 2014, 35(2): 134-136. |
[19] | LIU Xianghong, LUO Yushan, WANG Haijun. Study on Flow-Induced Vibration in Pipe Conveying Fluid with Orifice Plate[J]. Nuclear Power Engineering, 2013, 34(S1): 132-135,144. |
[20] | XIE En-fei, LIU Xi-chao, MING Qian. Analysis of Thermal and Hydro Characteristics of Steam Generator Blowdown System[J]. Nuclear Power Engineering, 2011, 32(S2): 13-17,22. |