[1] | Liu Zihua, Wang Di, Liang Ren, Cai Dechang, Ouyang Yong, Lin Zhikang, Tan Linhao. Numerical Study of Gas-Lead-Bismuth-Alloy Two-Phase Flow Characteristics in Vertical Circular Tube[J]. Nuclear Power Engineering, 2024, 45(1): 49-54. doi: 10.13832/j.jnpe.2024.01.0049 |
[2] | Liu Hao, Zhang Luteng, Zhou Wenxiong, Zhu Longxiang, Wan Lingfeng, Zhang Hong, Ma Zaiyong, Sun Wan, Pan Liangming, Deng Jiewen. Experimental Investigation on Void Fraction Distribution of Boiling Flow in 2×2 Rod Bundle Channel[J]. Nuclear Power Engineering, 2023, 44(6): 104-110. doi: 10.13832/j.jnpe.2023.06.0104 |
[3] | He Qingche, Zhang Luteng, Pan Liangming, Xu Wangtao, Yan Meiyue, Sun Wan, Ma Zaiyong. Study on Transition Criteria of Slug Flow to Churn Flow in Vertical Rectangular Channel Based on Characteristics of Interfacial Force[J]. Nuclear Power Engineering, 2023, 44(6): 127-133. doi: 10.13832/j.jnpe.2023.06.0127 |
[4] | Wang Kuo, Su Qianhua, Lu Donghua, Peng Fan, Xing Jun, Hong Rongkun. Experimental Research on Characteristics of Reactor Coolant Pump Torque under Two-Phase Conditions[J]. Nuclear Power Engineering, 2023, 44(6): 134-139. doi: 10.13832/j.jnpe.2023.06.0134 |
[5] | Zhang Haiying, Huang Zhong, Jiao Shaoyang, Dai Hongling, Xu Xiaogang, Sheng Feng. Analysis on Wearing of Bearing for Main Pump in Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(2): 108-111. doi: 10.13832/j.jnpe.2022.02.0108 |
[6] | Liu Shuai, Chen Cong, Liu Li, Gu Hanyang, Zhang Jiarong. Experimental Study on Flow Patterns and Void Fraction of Non-swirling and Swirling Gas-liquid Two-phase Flow Based on WMS[J]. Nuclear Power Engineering, 2022, 43(5): 43-50. doi: 10.13832/j.jnpe.2022.05.0043 |
[7] | Zhang Yongfa, Du Keyue, Cao Xiaxin, Fang Yuliang, Liu Xiaoya, Jiang Lizhi. Characteristic Analysis on Distribution of Void Fraction during Stable Flow Flashing Process under Low Pressure[J]. Nuclear Power Engineering, 2021, 42(6): 12-16. doi: 10.13832/j.jnpe.2021.06.0012 |
[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] | Jiang Tianze, Li Pengzhou, Ma Jianzhong. Fluidelastic Instability of Tube Bundles under Two-Phase Flow Subject to Unsteady Fluid Force[J]. Nuclear Power Engineering, 2019, 40(2): 58-61. doi: 10.13832/j.jnpe.2019.02.0058 |
[10] | Yang Yiang, Xiong Jinbiao, Zhang Tengfei, Chai Xiang, Liu Xiaojing. Measurement of Rectangular Channel Bubble Fraction Based on Wire-Mesh Technology[J]. Nuclear Power Engineering, 2019, 40(6): 203-206. doi: 10.13832/j.jnpe.2019.06.0203 |
[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] | LI Quan, Avramova M, LIu Yanghua, Zheng Meiyin, Zhao Yanli, Chen Jie, Jiao Yongjun, Yu Junchong. CFD Simulation of Subcooled Boiling in a Full-Size 5×5 Rod Bundle with Spacer Grids[J]. Nuclear Power Engineering, 2017, 38(S2): 25-28. doi: 10.13832/j.jnpe.2017.S2.0025 |
[13] | 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 |
[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] | Wu Xiangxiang, Huang Shanfang, Bai Su, Li Zhongchun, Li Songyu, Zhou Linglan, Jiang Guangming. Void Fraction Measurement in Vertical Slug Flow[J]. Nuclear Power Engineering, 2015, 36(2): 165-167. doi: 10.13832/j.jnpe.2014.02.0165 |
[16] | 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 |
[17] | Liu Guoqiang, Sun Licheng, Tian Daogui, Xing Dianchuan. Formation Mechanism of Radial Void Fraction Distribution of Bubbly Flow in A Vertical Circular Tube[J]. Nuclear Power Engineering, 2014, 35(1): 42-45,51. |
[18] | 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. |
[19] | SUN Shouhua, XU Taozhong, LI Ziyan, LI Jingsong, DENG Caiyu. Analysis of Loss of Offsite Power and Loss-of-flow Accident of HFETR[J]. Nuclear Power Engineering, 2013, 34(4): 111-113,125. |
[20] | 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. |