[1] | Zeng Yuan, Liang Jun, Xie Weirong, Wang Gang. Ultrasonic Measurement Technology and Application on 14-Foot Fuel Assembly Deformation[J]. Nuclear Power Engineering, 2024, 45(6): 106-111. doi: 10.13832/j.jnpe.2024.06.0106 |
[2] | Huang Su, He Xiaodong, Han Dadi, Liu Xinyuan, Li Benrong. EMI Analysis and Location of I&C Equipment in Nuclear Power Plant[J]. Nuclear Power Engineering, 2023, 44(1): 171-176. doi: 10.13832/j.jnpe.2023.01.0171 |
[3] | Zu Shuai, Chen Jie, Che Yinhui, Wang Guoshan, Zhao Qingsen, Zhang Qiang, Wu Zhenpeng. Study and Prevention of Steam Flow Induced Vibration of Nuclear Power Plant Condenser[J]. Nuclear Power Engineering, 2023, 44(2): 191-197. doi: 10.13832/j.jnpe.2023.02.0191 |
[4] | Zhang Shuanglei, Li Liangxing, Song Liming. Analysis and Optimization of Flow Field in an Axial Flow Lead-Bismuth Pump[J]. Nuclear Power Engineering, 2022, 43(3): 158-164. doi: 10.13832/j.jnpe.2022.03.0158 |
[5] | Li Kaiyu, Cai Qi, Cai Xinxin, Chen Yuqing, Peng Liu, Zhang Yifang. Application of Digital Twin Technology in the Design Phase of Floating Nuclear Power Plants[J]. Nuclear Power Engineering, 2022, 43(1): 197-201. doi: 10.13832/j.jnpe.2022.01.0197 |
[6] | Xiang Xianbao, Yang Quanchao, Wen Xue, Zheng Jiarong. Study on Fluid Flow and Heat Transfer in Seal Chamber of Hydrodynamic Mechanical Seals in Reactor Coolant Pump[J]. Nuclear Power Engineering, 2020, 41(6): 177-181. |
[7] | Guo Yiding, Guo Jian, Tan Mei. Simulation Analysis of Fuel Assembly Entering Floating Nuclear Reactor Core[J]. Nuclear Power Engineering, 2020, 41(3): 110-114. doi: 10.13832/j.jnpe.2020.03.0110 |
[8] | Liu Lizhi, Chen Jiu, Cai Longqi, Tan Shuyang, Zhao Xuecen. Analysis on Fluid Induced Vibration in Stop Valve of Piping System[J]. Nuclear Power Engineering, 2018, 39(S1): 15-19. doi: 10.13832/j.jnpe.2018.S1.0015 |
[9] | Luo Ting, Liu Caixue, Hu Jianrong, Yang Taibo, Jian Jie, Feng Jintao, Ai Qiong. Analysis and Diagnosis of Problem of Larger Amplitude with Core Barrel Beam Mode in a Nuclear Power Plant[J]. Nuclear Power Engineering, 2018, 39(3): 184-187. doi: 10.13832/j.jnpe.2018.03.0184 |
[10] | Liu Zhong, Song Mingliang, Wu Jiajie. Analysis of Typical Problems of DCS Non-Safety Class Software[J]. Nuclear Power Engineering, 2017, 38(3): 107-109. doi: 10.13832/j.jnpe.2017.03.0107 |
[11] | Xia Xin, Li Ning, Li Yan, Zhao Wei, Chen Xungang, He Peifeng. Distortion Oversize Analysis and Control Measures for Core Barrel[J]. Nuclear Power Engineering, 2016, 37(5): 71-74. doi: 10.13832/j.jnpe.2016.05.0071 |
[12] | Wang Guoqing. Failure Analysis and Treatment of Temperature Detector in Main Loop for Qinshan Phase Ⅱ NPP[J]. Nuclear Power Engineering, 2016, 37(6): 130-133. doi: 10.13832/j.jnpe.2016.06.0130 |
[13] | Zhou Mengjun, Mao Huihui, Feng Ya, Yang Lixin. PIV Experiment Research of Lateral Flow Field in 2×2 Rod Bundles Channel with Mixing Vane Grids[J]. Nuclear Power Engineering, 2016, 37(4): 133-137. doi: 10.13832/j.jnpe.2016.04.0133 |
[14] | 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 |
[15] | ZHENG Jiantao, LI Huaqi. Numerical Study on Effects of Shroud in Core Lower Plenum on Flow Field[J]. Nuclear Power Engineering, 2015, 36(1): 148-151. doi: 10.13832/j.jnpe.2015.01.0148 |
[16] | Zhang Hongliang, Liu Haipeng, Fang Caishun, Lu Chuan. Optimization Design of Reactor Lower Plenum[J]. Nuclear Power Engineering, 2014, 35(3): 59-63. doi: 10.13832/j.jnpe.2014.03.0059 |
[17] | HE Peifeng, WANG Qingtian, ZHANG Yi, MU Dianpeng, LI Yan, LI Ning. Analysis and Control of Welding Deformation of Nuclear Power Reactor Plant CRDM Anti-Seismic Ring[J]. Nuclear Power Engineering, 2013, 34(S1): 109-111,119. |
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[19] | YAN Jing, WANG Wei. Study on Refueling Pattern and Its Application in Tianwan Nuclear Power Plant[J]. Nuclear Power Engineering, 2012, 33(1): 107-111,133. |
[20] | LU Chuan, ZHANG Yong, LU Jian-chao, DONG Hua-ping. Analysis of Flow Behavior of Coolant in Natural Circulation Reactor Based on Computational Fluid Dynamics[J]. Nuclear Power Engineering, 2012, 33(S1): 111-114,118. |