[1] | He Mengfu, Zhang Yiming, Qin Manqing, Xu Zili, Liao Tongtong. Research on Vibration Measurement Method of Nuclear Power Plant Pipeline Based on Unmarked Vision Algorithm[J]. Nuclear Power Engineering, 2024, 45(4): 221-227. doi: 10.13832/j.jnpe.2024.04.0221 |
[2] | 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 |
[3] | Yang Jichen, Song Mingliang, Liang Congcong, Li Zhen, Cao Binbin, Sun Jun. Analysis and Treatment of Abnormal Vibration of High Pressure Heater to Deaerator Pipeline[J]. Nuclear Power Engineering, 2018, 39(S2): 142-145. doi: 10.13832/j.jnpe.2018.S2.0142 |
[4] | Feng Zhipeng, Wu Wanjun, Xiong Furui, Zhang Wenzheng, Lyu Xi, Song Haiyang, Wang Bihao. Study on Pump Induced Vibration Acoustics of Reactors[J]. Nuclear Power Engineering, 2018, 39(3): 151-155. doi: 10.13832/j.jnpe.2018.03.0151 |
[5] | Yang Zhang, Wang Hexu, Jiang Yanlong, Sun Chengbin. Diagnose and Treatment of Charging Pump Cavitation in Nuclear Power Stations[J]. Nuclear Power Engineering, 2016, 37(4): 77-80. doi: 10.13832/j.jnpe.2016.04.0077 |
[6] | Zeng Xiaokang, Zhou Huihui, Xiong Wanyu. CFD Study on Cavitation Abrasion for Axletree of Main Pump of Tianwan NPP[J]. Nuclear Power Engineering, 2016, 37(2): 143-146. doi: 10.13832/j.jnpe.2016.02.0143 |
[7] | 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 |
[8] | Xu Zhaoping. Experimental Analysis of RRA System Performance at Atmospheric Pressure[J]. Nuclear Power Engineering, 2015, 36(S1): 118-121. doi: 10.13832/j.jnpe.2015.S1.0118 |
[9] | Zhao Yue, He Chao, Xu Weizu, Wei Chao, Bao Yu. Improvement of Vibration Measurement for Nuclear-Class Pipes in Nuclear Power Plants during Decommissioning[J]. Nuclear Power Engineering, 2015, 36(5): 111-113. doi: 10.13832/j.jnpe.2015.05.0111 |
[10] | 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 |
[11] | 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 |
[12] | 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. |
[13] | 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. |
[14] | YE Zhangliu, LIU Xichao, XIE Enfei. Analysis of Choked Flow in Control Valves[J]. Nuclear Power Engineering, 2013, 34(S2): 93-96. |
[15] | MA Na, YIN Chang-geng, QIN Jin-guang. Wall Thinning Analysis of Carbon Steel Pipes in Nuclear Power Plants[J]. Nuclear Power Engineering, 2013, 34(2): 123-125. |
[16] | 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. |
[17] | YUAN Shaobo, YU Danping, ZHOU Zhengping, XI Zhide, ZHAO Hui, HE Chao. Assessment and Reducer of Pipe Vibration of Tianwan NPP[J]. Nuclear Power Engineering, 2012, 33(6): 6-8. |
[18] | LI Gang, LIANG Bingbing, YIN Haifeng. Research on Process Pipe Vibration Improvements in NPP Conventional Island[J]. Nuclear Power Engineering, 2012, 33(6): 93-95,100. |
[19] | WANG Xiuli, YUAN Shouqi, ZHU Rongsheng, YU Zhijun. Numerical Analysis for Causes of Cavitation Fracture Working Condition on Centrifugal Pump[J]. Nuclear Power Engineering, 2012, 33(6): 101-104,114. |
[20] | HE Chao, YUAN Shao-bo, YU Dan-ping. Analysis of Evaluation Methods for NPP Piping System Vibration[J]. Nuclear Power Engineering, 2011, 32(S1): 107-109,124. |