[1] | 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 |
[2] | 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 |
[3] | 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 |
[4] | Liang Lehua, Wang Xuejian, Zeng Wenjie, Li Chuhao. Quantitative Research on Parameter Uncertainty of Helical Coil Once-Through Tube Steam Generator on the Small Pressurized Water Reactor[J]. Nuclear Power Engineering, 2023, 44(3): 152-159. doi: 10.13832/j.jnpe.2023.03.0152 |
[5] | Qi Peiyao, Deng Jian, Tan Sichao, Qiu Feng, Yu Xiaoyong. Research on Flow Field in Rod Bundle Channel under Low Reynolds Number Using PIV Technique[J]. Nuclear Power Engineering, 2021, 42(1): 18-22. doi: 10.13832/j.jnpe.2021.01.0018 |
[6] | 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 |
[7] | 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. |
[8] | Zang Jinguang, Yan Xiao, Li Yongliang, Huang Zhigang, Huang Yanping. Error Sensitive Analysis for Circular Pipe Heat Transfer Experiments with Supercritical Water[J]. Nuclear Power Engineering, 2016, 37(6): 15-17. doi: 10.13832/j.jnpe.2016.06.0015 |
[9] | Chen Jiayue, Xiong Zhenqin, Xiao Yao, Gu Hanyang. Experimental Study on Convective Heat Transfer of Supercritical R134a in Vertical Circular Tubes[J]. Nuclear Power Engineering, 2016, 37(2): 27-31. doi: 10.13832/j.jnpe.2016.02.0027 |
[10] | Zang Jinguang, Du Daiquan, Yan Xiao, Huang Shanfang, Huang Yanping, Yu Junchong. Verification and Analysis of CSR1000 Subchannel Code with Wire Wrap Model[J]. Nuclear Power Engineering, 2014, 35(6): 26-30. doi: 10.13832/j.jnpe.2014.06.0026 |
[11] | 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. |
[12] | ZHU Fa-wen, LEI Tao, CHENG Hua-yang, PANG Hua, PENG Yuan, RU Jun. Supercritical Fuel Assembly Design Applicable for Cruciform Control Rod[J]. Nuclear Power Engineering, 2013, 34(1): 35-39. |
[13] | LI Yu-guang, WANG Xiao-bin, LUO Ying, YANG Min, LI Xiang, FU Qiang. Analysis on Heat Transfer of Outlet Nozzle and Steam Cavity for SCWR RPV Using CFD[J]. Nuclear Power Engineering, 2013, 34(1): 65-70. |
[14] | HUANG Zhi-gang, CENG Xiao-kang, LI Yong-liang, YAN Xiao, XIAO Ze-jun, HUANG Yan-ping. Summarization and Evaluation of Supercritical Heat Transfer Correlations[J]. Nuclear Power Engineering, 2012, 33(S1): 28-31. |
[15] | XIONG Ting, YAN Xiao, HUANG Shan-fang, HUANG Yan-ping. Analysis of Flow Instability Types and Dynamic Behaviors for Supercritical Water[J]. Nuclear Power Engineering, 2012, 33(S1): 37-40,44. |
[16] | ZENG Xiaokang, YAN Xiao, LI Yongliang, HUANG Yanping, XIAO Zejun. Study on Time-Averaged Turbulent Conservation Equations under Supercritical Condition[J]. Nuclear Power Engineering, 2012, 33(2): 56-61. |
[17] | ZHU Hongye, YANG Xingtuan, JU Huaiming, JIANG Shengyao. Analysis of Flow Excursion Instabilities in Helically Coiled Tube Steam Generator of High Temperature Gas-Cooled Reactor[J]. Nuclear Power Engineering, 2012, 33(4): 76-80. |
[18] | WANG Weishu, ZHU Xiaojing, BI Qincheng, WU Gang, YU Shuiqing. Study on Frictional Pressure Drop of Steam-Water Two Phase Flow in Optimized Four-Head Internal-Ribbed Tube[J]. Nuclear Power Engineering, 2012, 33(3): 38-41. |
[19] | ZHANG Hao, XIE Zhengrui, YANG Yanhua. Study on Turbulence Model of Supercritical Fluids Flow and Heat Transfer under Strong Buoyancy[J]. Nuclear Power Engineering, 2011, 32(1): 63-69. |
[20] | DENG Zhian, LUO Yushan, WANG Haijun, CHEN Tingkuan, WU Yuan. Research on Pressure-Drop Type Instabilities Between Different Parallel Vertical Rifled Tubes at Lower Mass Velocity[J]. Nuclear Power Engineering, 2011, 32(2): 68-71,85. |