[1] | Wang Xuejian, Zhao Yanan, Yu Tao. Numerical Simulation of Pressure and Temperature Fields in Rectangular Narrow Channel under Blistering Condition[J]. Nuclear Power Engineering, 2024, 45(2): 82-87. doi: 10.13832/j.jnpe.2024.02.0082 |
[2] | Liu Yirui, Dong Xiuchen, Zhang Xin, Yuan Jiangtao. Numerical Analysis of Flow Distribution Characteristics at Core Inlet of Small Reactor under Rolling Condition[J]. Nuclear Power Engineering, 2022, 43(5): 89-94. doi: 10.13832/j.jnpe.2022.05.0089 |
[3] | He Gening, Li Xiaojia, Cong Tenglong, Chen Yiran, Li Donghui, Wu Ge. Investigation on Reversed Flow Characteristics of U-Tube Steam Generator under Ocean Conditions[J]. Nuclear Power Engineering, 2021, 42(3): 37-42. doi: 10.13832/j.jnpe.2021.03.0037 |
[4] | Deng Yonghao, Xu Wei, Liu Xiaojing, Guo Jiuyuan, Wu Dan. Experimental Study of Bottom Reflooding in a Narrow Rectangular Channel[J]. Nuclear Power Engineering, 2021, 42(6): 17-23. doi: 10.13832/j.jnpe.2021.06.0017 |
[5] | Wang Weishu, Huang Zhihao, Xu Weihui, Ma Ziqiang, Zhu Xiaojing, Bi Qincheng. Experiemental Study on Heat Transfer of Supercritical Water in Triangular Channel of Reactor Core with Spacer Grid[J]. Nuclear Power Engineering, 2021, 42(5): 90-95. doi: 10.13832/j.jnpe.2021.05.0090 |
[6] | Chen Chong, Meng Qingzheng, Wu Wei, Liu Dongmin, Gao Puzhen. Prediction Model of Boiling Heat Transfer Coefficient in Rectangular Narrow Channel[J]. Nuclear Power Engineering, 2017, 38(2): 175-178. doi: 10.13832/j.jnpe.2017.02.0175 |
[7] | Xu Weihui, Ma Ziqiang, Wang Weishu, Cui Qiang, Zhu Xiaojing, Lu Tong, Bi Qincheng. Experimental Investigation on Heat Transfer of Supercritical Pressure Water Flowing in Sub-Channel with Triangle Distribution in Reactors[J]. Nuclear Power Engineering, 2017, 38(2): 24-27. doi: 10.13832/j.jnpe.2017.02.0024 |
[8] | Zhu Haiyan, Yan Xiao, Li Yongliang, Huang Yanping, Xiao Zejun. Experimental Research on Heat Transfer of Supercritical Water in Square Annular Channel[J]. Nuclear Power Engineering, 2017, 38(6): 18-22. doi: 10.13832/j.jnpe.2017.06.0018 |
[9] | Shi Yan, Yang Fuming, Li Yuquan. Scaling Analysis of the Transient from Forced Circulation to Natural Circulation[J]. Nuclear Power Engineering, 2016, 37(2): 38-42. doi: 10.13832/j.jnpe.2016.02.0038 |
[10] | Luo Feng. Experimental Investigation on Heat Transfer Characteristic of Saturated Boiling in Round Tube[J]. Nuclear Power Engineering, 2015, 36(S1): 184-186. doi: 10.13832/j.jnpe.2015.S1.0184 |
[11] | ZHANG Liqin, HUANG Yanping, WANG Junfeng, SONG Mingliang, ZAN Yuanfeng. Experimental Investigation on Wake Characteristics of Single Air Bubble Rising in Vertical Narrow Rectangular Channel[J]. Nuclear Power Engineering, 2015, 36(6): 32-36. doi: 10.13832/j.jnpe.2015.06.0032 |
[12] | ZHANG Liqin, HUANG Yanping, WANG Junfeng, SONG Mingliang, ZAN Yuanfeng. Comparative Investigation on Wake Characteristics of an Vapor and Air Bubble Rising in a Vertical Narrow Rectangular Channel[J]. Nuclear Power Engineering, 2015, 36(6): 37-40. doi: 10.13832/j.jnpe.2015.06.0037 |
[13] | Xu Weihui, Wang Weishu, Liang Chengsheng, Lu Tong, Wang Han, Wang Linchuan, Bi Qincheng. Experimental Investigation on Heat Transfer Characteristics of Subcritical Pressure Water Flowing in Subchannel with Square Distribution in SCWR[J]. Nuclear Power Engineering, 2014, 35(6): 17-20. doi: 10.13832/j.jnpe.2014.06.0017 |
[14] | Song Mingliang, Huang Yanping, Wang Junfeng, Liu Guangxu, Zhang Liqin, Zhang Xingwu. Experimental Investigation of Air Bubble in Water through a Vertical Narrow Rectangular Channel[J]. Nuclear Power Engineering, 2014, 35(5): 74-77. doi: 10.13832/j.jnpe.2014.05.0074 |
[15] | WANG Chang, GAO Pu-zhen, TAN Si-chao, HUANG Yan-ping. Effect of Rolling Motion on Forced Circular Boiling Flow Characteristics[J]. Nuclear Power Engineering, 2013, 34(2): 51-55. |
[16] | WANG Chang, GAO Puzhen, TAN Sichao, HUANG Yanping. Analysis on Characteristic of Forced Circulation Flow Rate Pulsation under Rolling Condition[J]. Nuclear Power Engineering, 2012, 33(3): 56-60. |
[17] | LIU Xiao-zhong, HUANG Yan-ping, MA Jian, HUANG Jun. Frictional Resistance Characteristics of Single-Phase Flow in Narrow Rectangular Channel with Rolling Motion[J]. Nuclear Power Engineering, 2012, 33(S1): 54-58. |
[18] | WANG Tao, WANG Jun, WANG Xiaojun. Experimental Study on Two-Phase Flow and Heat Transfer through Narrow Rectangular Channel under Middle-Low Pressure Condition[J]. Nuclear Power Engineering, 2012, 33(4): 96-101. |
[19] | ZHOU Lei, LIU Xiangfeng, YAN Xiao, HUANG Yanping, CHEN Bingde. Numerical Prediction of Critical Heat Flux in Narrow Rectangular Channels[J]. Nuclear Power Engineering, 2011, 32(4): 46-51. |
[20] | LIU Xiao-zhong, HUANG Yan-ping, MA Jian, HUANG Jun. Study on Friction Resistance Characteristics of Narrow Rectangular Channel Single-Phase Isothermal Flow in Heaving Motion[J]. Nuclear Power Engineering, 2011, 32(6): 71-75. |