[1] | Zhu Tenghao, Wang Hongtao, Wang Haitao. Research on Vibration-induced Noise Simulation of Main Control Room of High-temperature Gas-cooled Reactor[J]. Nuclear Power Engineering, 2024, 45(6): 132-138. doi: 10.13832/j.jnpe.2024.06.0132 |
[2] | Ni Man, Zhao Jun, Qian Hongtao, Zhang Jiajia, Gong Yu, Xiao Jun. Study on Risk-informed SSC Safety Classification of High Temperature Gas-cooled Reactor[J]. Nuclear Power Engineering, 2024, 45(3): 193-198. doi: 10.13832/j.jnpe.2024.03.0193 |
[3] | Cai Yuntong, Zhao Houjian, Li Xiaowei, Su Yang, Lu Yiming, Guo Zhangpeng, Liu Fang. Modified SST k-ω-γ Model and Prediction of Laminar to Turbulent Flow Transition in Helical Tube[J]. Nuclear Power Engineering, 2024, 45(6): 55-62. doi: 10.13832/j.jnpe.2024.06.0055 |
[4] | Xian Lin, Cheng Kun, Ran Xu, Wu Dan, Yan Junjie, Qiao Shouxu. Study on Two-Phase Flow Instability in Helical Tube under Rolling Condition[J]. Nuclear Power Engineering, 2024, 45(5): 85-91. doi: 10.13832/j.jnpe.2024.05.0085 |
[5] | Zheng Pengde, Tang Qifen, Li Zhenzhong, Wang Ningyuan, Chen Deqi. Experimental Study on Boiling Two-Phase Flow Instability in a Single Helically Coiled Tube[J]. Nuclear Power Engineering, 2024, 45(4): 61-68. doi: 10.13832/j.jnpe.2024.04.0061 |
[6] | Fei Likai, Zhang Peng, He D, an, Yuan Haowei, Hu Fuquan, Cui Lei, Shen Feng, Liu Lifang. Experimental Investigation of Counter-Current Flow in Downcomer of CAP1400[J]. Nuclear Power Engineering, 2021, 42(2): 60-64. doi: 10.13832/j.jnpe.2021.02.0060 |
[7] | Wang Cong, Zhang Wei, Li Jingsong, Qiao Pengrui, Shi Huilie. A Method Study of Numerical Simulation on Flow Field of Spiral Tube in Steam Generator Shell Side[J]. Nuclear Power Engineering, 2021, 42(4): 171-175. doi: 10.13832/j.jnpe.2021.04.0171 |
[8] | Shen Pingchuan, Liu Qing, Qi Huanhuan, Huang Xuan, Liu Jian, Chen Guo. Study on Flow-Induced Vibration Damping Simulation of Heat Exchanger Tube in Non-Uniform Two-Phase Flow[J]. Nuclear Power Engineering, 2020, 41(6): 116-119. |
[9] | Feng Xiaodong, Su Wentao, Ma Yu, Wang Lei, Li Xiaobin. Analysis of Flow-Induced Vibration of HP-Cooler Coil on Reactor Coolant Pump[J]. Nuclear Power Engineering, 2020, 41(6): 101-105. |
[10] | Liu Yang, Wang Jun. Heat Transfer Simulation of Fuel Transport Cask for High Temperature Gas Cooled Reactor[J]. Nuclear Power Engineering, 2017, 38(5): 160-163. doi: 10.13832/j.jnpe.2017.05.0160 |
[11] | Xiao Xiu, Zhu Qingzi, Chen Shaowen, Zhang Yajun, JiA Haijun, Mamoru ishii. Investigation of Vibration Amplitude Effect on Local Flow Parameters of Two-Phase Flow[J]. Nuclear Power Engineering, 2017, 38(2): 38-42. doi: 10.13832/j.jnpe.2017.02.0038 |
[12] | Jiang Tianze, Li Pengzhou, Ma Jianzhong, Gao Lixia, Lai Jiang. Three Key Mechanical Problems of Flow Induced Vibration of Tube Bundles in Two-Phase Flow[J]. Nuclear Power Engineering, 2016, 37(S2): 14-19. doi: 10.13832/j.jnpe.2016.S2.0014 |
[13] | Zhou tao, Qi Shi, Song mingqiang, Chen baixu, Huang yanpin, Xiao zejun. Experimental Study on Flow Excursion of Two Phase Natural Circulation under Low Pressure in Narrow Rectangular Channel[J]. Nuclear Power Engineering, 2016, 37(4): 1-5. doi: 10.13832/j.jnpe.2016.04.0001 |
[14] | Chen Deqi, Wang Qinghua, Lu Qi, Pan Liangming. Visual Experimental Investigation on Oscillations of Pressure Drop and Flow Rate of Two-Phase Flow in Mini-Channel[J]. Nuclear Power Engineering, 2015, 36(5): 187-193. doi: 10.13832/j.jnpe.2015.05.0187 |
[15] | Li Yongchun, Liu Xiaojing, Cheng Xu. Experimental Study on Local Two Phase Distributions in ERVC Flow Channel[J]. Nuclear Power Engineering, 2014, 35(5): 153-156. doi: 10.13832/j.jnpe.2014.05.0153 |
[16] | Wang Shuxiang, Niu Zhiyuan, Zhang Wei, XU Jinliang. Experimental Investigations on Heat Transfer of Supercritical CO2 Flowing Through A Helically Coiled Tube[J]. Nuclear Power Engineering, 2014, 35(1): 28-31. |
[17] | XING Dian-chuan, YAN Chang-qi, SUN Li-cheng, JIN Guang-yuan, WANG Guang-fei. Study on Homogeneous Flow Model for Air-Water Two-Phase Flow in Mini-Rectangular Channel[J]. Nuclear Power Engineering, 2013, 34(3): 82-86. |
[18] | JIANG Nai-bin, ZANG Feng-gang, ZHANG Yi-xiong, GUAN Hui. Research on Void Fraction Models for Vertically Upward Two-Phase Cross-Flow in Horizontal Tube Bundle[J]. Nuclear Power Engineering, 2013, 34(3): 67-70. |
[19] | TANG Zhen-wei, YANG Xing-tuan, SUN Yu-liang, WANG Wen-jun, LIU Zhi-yong. Experiment of Pebble Flow in Two-Region Pebble-Bed Reactor Core Vessel[J]. Nuclear Power Engineering, 2013, 34(3): 105-108,112. |
[20] | MAO Yu-fei, GUO Lie-jin, BAI Bo-feng, ZHEN Fei-qiang, GUO Meng. Experimental Investigation on Frictional Pressure Drop of Single-Phase Water in Helical Coils at High and Supercritical Pressure[J]. Nuclear Power Engineering, 2012, 33(S1): 80-84. |