[1] | Zhang Jing, Wang Mingjun, Tian Wenxi, Su Guanghui, Qiu Suizheng. Application of Artificial Intelligence Algorithms in Thermal-Hydraulic Analysis of Nuclear Reactors[J]. Nuclear Power Engineering, 2025, 46(2): 127-140. doi: 10.13832/j.jnpe.2024.090039 |
[2] | Chen Yongchao, Wei Xingfang, Liu Yanwu, Fang Jian, Ran Xiaobing. Experimental and CFD Simulation of the RPV Head Plenum[J]. Nuclear Power Engineering. doi: 10.13832/j.jnpe.2024.070004 |
[3] | Chen Xi, Wang Xiaoyu, Cui Cong, Deng Jian, Liu Yu, Liu Luguo, Liang Yu, Peng Huanhuan. Research on Thermal Diffusion Performance of Fuel Assembly Spacer Grid Based on Numerical Methodology[J]. Nuclear Power Engineering, 2024, 45(6): 91-97. doi: 10.13832/j.jnpe.2024.06.0091 |
[4] | Zhang Ji, Wang Yingjie, Wang Mingjun, Tian Wenxi, Qiu Suizheng, Su Guanghui. Study on Jet Mixing Characteristics of Lead-Bismuth Eutectic Cooled Reactor Assembly Head Based on CFD Method[J]. Nuclear Power Engineering, 2024, 45(4): 77-86. doi: 10.13832/j.jnpe.2024.04.0077 |
[5] | Deng Jian, Wei Zonglan, Zeng Wei, Li Songwei, Qiu Zhifang, Liu Luguo. Development and Application of Autonomous Computational Fluid Dynamics Code WINGS-CFD for Nuclear Reactors[J]. Nuclear Power Engineering, 2024, 45(S2): 63-69. doi: 10.13832/j.jnpe.2024.S2.0063 |
[6] | Zhao Hongwei, Dong Rui, Li Junjie, Ouyang Zhengrong, Heng Yuekun. Numerical Simulation of Displacement Process of Liquid Scintillator and Ultrapure Water in a Large Diameter Spherical Tank[J]. Nuclear Power Engineering, 2024, 45(2): 225-230. doi: 10.13832/j.jnpe.2024.02.0225 |
[7] | Liu Zhenglong, Qiu Hanrui, Wang Mingjun, Sun Hao, Tian Wenxi, Su Guanghui. Simulation of Blockage Accident of LBE-Cooled Fast Reactor Fuel Assembly Based on Mesh Deformation Method[J]. Nuclear Power Engineering, 2024, 45(3): 95-103. doi: 10.13832/j.jnpe.2024.03.0095 |
[8] | Xin Sufang, Wu Dan, Shen Yaou, Ren Chunming, Chen Shilong. Characterization Analysis of Core Outlet Temperature Measurement in Nuclear Power Plants[J]. Nuclear Power Engineering, 2023, 44(3): 237-242. doi: 10.13832/j.jnpe.2023.03.0237 |
[9] | Lu Dingsheng, Wang Chen, Wang Chenglong, Yue Nina, Yang Ping, Tian Wenxi, Su Guanghui, Qiu Suizheng. Study on Oxidation Corrosion Characteristics of Horizontal Lead-Bismuth Reactor Core[J]. Nuclear Power Engineering, 2023, 44(3): 96-103. doi: 10.13832/j.jnpe.2023.03.0096 |
[10] | Zeng Fulin, Zhang Xiaolong, Zhao Pengcheng. Study on Circumferential Non-Uniformity of Annular Fuel Outer Temperature Distribution in Lead-bismuth Cooled Tight Cell[J]. Nuclear Power Engineering, 2023, 44(6): 95-103. doi: 10.13832/j.jnpe.2023.06.0095 |
[11] | Wen Shuang, Zeng Xiehu, Wen Qinglong, Ruan Shenhui, Zhang Ruiqian, Wei Tianguo, Yang Hongyan. Numerical Study on Typical Cell of Fuel Assembly by Turbulence Excitation[J]. Nuclear Power Engineering, 2023, 44(1): 9-16. doi: 10.13832/j.jnpe.2023.01.0009 |
[12] | Su Qianhua, Fan Guanhua, Lyu Lulu, Lu Donghua, Yang Ping, Gan Fujun, Yan Binghuo, Wang Chengyue. Effect of the Arrangement for Grid Spacers with Mixing Vanes on the Thermal Hydraulic Characteristics of a 5×5 Rod Bundle via CFD Analysis[J]. Nuclear Power Engineering, 2023, 44(4): 88-94. doi: 10.13832/j.jnpe.2023.04.0088 |
[13] | Yang Tao, Zhao Pengcheng, Zhao Yanan, Yu Tao. Development of Reduced-Order Thermal Stratification Model for Upper Plenum of Lead-Bismuth Fast Reactor Based on CFD[J]. Nuclear Power Engineering, 2023, 44(2): 48-53. doi: 10.13832/j.jnpe.2023.02.0048 |
[14] | Li Jinyang, Ma Jun, Qiao Shouxu, Hao Sijia, Li Xupeng, Tan Sichao, Tian Ruifeng. Investigation on Characteristics of Resistance and Flow Distribution of 5×5 Annular Fuel Rod Bundle Channel under Pulsating Flow Condition[J]. Nuclear Power Engineering, 2023, 44(6): 111-118. doi: 10.13832/j.jnpe.2023.06.0111 |
[15] | Chen Mingrui, Wei Zonglan, Chen Chong, Deng Jian, Zhu Li, Peng Shinian. Numerical Simulation of Flow Heat Transfer in Rectangular Channel under Local Deformation Condition[J]. Nuclear Power Engineering, 2023, 44(3): 223-230. doi: 10.13832/j.jnpe.2023.03.0223 |
[16] | Liang Ruixian, Yang Lingfeng, Wang Yifeng, Li Xiaobo, Niu Fenglei. Numerical Study on Oxygen Transport Characteristics in Liquid Lead-Bismuth Eutectic Circuit[J]. Nuclear Power Engineering, 2022, 43(6): 187-194. doi: 10.13832/j.jnpe.2022.06.0187 |
[17] | Ren Bing, Gan Fujun, Yang Ping. CFD Calculation and Analysis of Boiling Heat Transfer of Full-length Fuel Bundle with Bent Rod[J]. Nuclear Power Engineering, 2022, 43(6): 43-50. doi: 10.13832/j.jnpe.2022.06.0043 |
[18] | Hu Shiqu, Gu Kai, Sun Xinyu, Yuan Jingqi, Dong He, Hui Jiuwu. Numerical Simulations of Flow Field in First-Stage Steam-water Separator of Steam Generator[J]. Nuclear Power Engineering, 2022, 43(5): 7-11. doi: 10.13832/j.jnpe.2022.05.0007 |
[19] | Hou Jianfei, Wang Qingli, Si Hengyuan. Analysis of Post-Accident Debris Transport Performance in In-Containment Refueling Water Storage Tank in Nuclear Power Plants[J]. Nuclear Power Engineering, 2021, 42(5): 76-80. doi: 10.13832/j.jnpe.2021.05.0076 |
[20] | Jiang Hong, Zhou Jing, Liu Lizhi. Numerical Analysis on the Characteristics of Steam Condensation in Presence of Air under Vertical Tube Bundle Conditions[J]. Nuclear Power Engineering, 2019, 40(5): 41-45. |