[1] | Ma Youfu, Han Linfeng, Wen Huiming, Lyu Junfu, Wang Shuo. Experimental Study on Gas-Liquid Counter Current Flow Limitation in Inclined Pipes[J]. Nuclear Power Engineering, 2024, 45(3): 51-59. doi: 10.13832/j.jnpe.2024.03.0051 |
[2] | Yang Chao, Li Zhipeng, Yu Tao, Chen Zhenping. Research on Ray Effect Method Based on Global Factor Correction for First Collision Source[J]. Nuclear Power Engineering, 2023, 44(3): 54-58. doi: 10.13832/j.jnpe.2023.03.0054 |
[3] | Wang Jue, Chen Lisheng, Liu Jiange, Hu Chen, Cai Qi. Evaluation of Condensation Heat Transfer Coefficient of Stable Steam Jet Submerged in Water[J]. Nuclear Power Engineering, 2021, 42(4): 27-32. doi: 10.13832/j.jnpe.2021.04.0027 |
[4] | Chen Bowen, Wang Bo, Tian Ruifeng, Li Ru. Experimental Study on Spread of Droplet Impacting on Dry Inclined Wall[J]. Nuclear Power Engineering, 2020, 41(4): 64-69. |
[5] | Wang Jun. Correction of CPPF Factor in QINSHAN CANDU Reactor[J]. Nuclear Power Engineering, 2020, 41(5): 8-11. |
[6] | Cao Zhiwei, Liu Jianchang, Xiao Hong, Yang Jiang, Lu Xianghui, Tian Wenxi. Effect of Inclination Condition on LOCA for a Small Offshore Reactor[J]. Nuclear Power Engineering, 2019, 40(5): 118-123. |
[7] | Liu Shenghui, Huang Yanping, Liu Guangxu, Wang Junfeng, Wang Jinyu. Influence of Gas State Equations on Acceleration Parameter for Heat Transfer to Supercritical Carbon Dioxide Flowing in Heated Tubes[J]. Nuclear Power Engineering, 2019, 40(1): 18-22. doi: 10.13832/j.jnpe.2019.01.0018 |
[8] | Li Yuanming, Tang Changbing, Yu Hongxing, Chen Ping, Zhou Yi. Numerical Simulation Research on Equivalent Thermal Conductivity Coefficient of M3 Fuel[J]. Nuclear Power Engineering, 2018, 39(2): 76-79. doi: 10.13832/j.jnpe.2018.02.0076 |
[9] | Guo Rui, Liu Xiaojing, Cheng Xu, Yu Hongxing. Theoretical Investigation on Critical Heat Flux at Inclined Heater Surface in Low Pressure[J]. Nuclear Power Engineering, 2016, 37(4): 11-14. doi: 10.13832/j.jnpe.2016.04.0011 |
[10] | Xie Tianzhou, Chen Bingde, Xu Jianjun, Bao Wei. Flow Patterns Transition in Vertical and Upwardly Inclined Two-Phase Flow[J]. Nuclear Power Engineering, 2015, 36(4): 4-7. doi: 10.13832/j.jnpe.2015.04.0004 |
[11] | Liu Wenxing, Peng Jingfeng, Xu Jianjun, Huang Yanping, Yang Zumao. Theoretical Study on Effect of Flow Channel Local Inclination on Critical Heat Flux[J]. Nuclear Power Engineering, 2015, 36(4): 8-11. doi: 10.13832/j.jnpe.2015.04.0008 |
[12] | DU Juan, Shao Xuejiao, Zhang Liping, Kan Qianhua, Guo Sujuan. Research on Elastoplastic Strain Correction Factor of Titanium Alloy[J]. Nuclear Power Engineering, 2014, 35(1): 101-105. |
[13] | Gong Houjun, Yang Xingtuan, Huang Yanping, Jiang Shengyao, Liu Zhiyong. Experimental and Numerical Study on Natural Circulation of Integrated Reactor under Inclination Conditions[J]. Nuclear Power Engineering, 2014, 35(5): 89-93. doi: 10.13832/j.jnpe.2014.05.0089 |
[14] | Yan Chaoxing, Yan Changqi, SuN Licheng, Xing Dianchuan, Wang Yang. Effects of Inclination and Rolling on Interfacial Parameter Distributions of Bubbly Flow in a Rectangular Duct[J]. Nuclear Power Engineering, 2014, 35(5): 83-88. doi: 10.13832/j.jnpe.2014.05.0083 |
[15] | YANG Xing-tuan, ZHU Hong-ye, GONG Hou-jun, LIU Zhi-yong, JIANG Sheng-yao. Natural Circulation Characteristics in a Symmetrical Two-Circuit Loop under Inclined Condition[J]. Nuclear Power Engineering, 2013, 34(5): 124-127. |
[16] | WEN Qinglong, CHEN Jun, LU Donghua, ZHAO Hua. Visual Experimental Study on Bubble Behavior on Inclined Downward Facing Surfaces[J]. Nuclear Power Engineering, 2012, 33(3): 51-55. |
[17] | XING Dianchuan, SUN Licheng, YAN Changqi, WANG Xin, SUN Bo. Experimental Investigation on Characteristics of Void Fraction for Bubbly Flow in an Inclined Circular Tube[J]. Nuclear Power Engineering, 2012, 33(4): 111-115. |
[18] | WEN Qing-long, CHEN Jun, ZHAO Hua. Experimental Study on Pool Boiling Critical Heat Flux in Inclined Confined Spaces[J]. Nuclear Power Engineering, 2011, 32(6): 34-37. |
[19] | WEN Qinglong, CHEN Jun, ZHAO Hua. Flow Pattern Characteristics of Pool Boiling in Inclined Confined Spaces[J]. Nuclear Power Engineering, 2011, 32(1): 104-107,121. |
[20] | DU Sijia, ZHANG Hong, JIA Baoshan. Experimental Research on Single-Phase Heat Transfer Characteristics in a Vertical Circular Tube under Marine Conditions[J]. Nuclear Power Engineering, 2011, 32(3): 92-96,101. |