[1] | Jin Guangyuan, Bai Jinghu, Wang Rui, Li Weilian, Du Lipeng, Zhang Wenchao. Research on Disturbance Wave Characteristics of Annular Flow on Edge and Corner Rods of Rod Bundle Channel[J]. Nuclear Power Engineering, 2025, 46(1): 143-151. doi: 10.13832/j.jnpe.2025.01.0143 |
[2] | Xu Yujie, Mo Jinhong, Dong Xiaomeng, Liu Yong, Xu Anqi, Yu Yang. Research on Parameter Prediction for Transient Conditions in Rod Bundle Subchannel Based on POD-ML Method[J]. Nuclear Power Engineering, 2025, 46(2): 177-185. doi: 10.13832/j.jnpe.2024.080031 |
[3] | Duan Bingqi, Zhao Meng, Zhang Hao, Chai Xiang, Yang Yanhua. Validation and Verification of COSINE Code Based on Rod Bundle Heat Transfer Experiment[J]. Nuclear Power Engineering, 2024, 45(1): 19-26. doi: 10.13832/j.jnpe.2024.01.0019 |
[4] | Liu Shasha, Ma Zaiyong, Zhang Rui, Sun Wan, Zhang Luteng, Zhu Longxiang, Pan Liangming. Experimental Study on Axial Evolution Characteristics of Single-phase Turbulent Mixing in Rod Bundle Sub-channels with Grids[J]. Nuclear Power Engineering, 2024, 45(3): 104-109. doi: 10.13832/j.jnpe.2024.03.0104 |
[5] | Wu Change, Zhang Yuxiang, Chen Changyi, Jiang Li, Shan Jianqiang, Fu Xiangang. Study on CHF Relational Expression Development Based on High-precision Subchannel Code[J]. Nuclear Power Engineering, 2024, 45(4): 45-52. doi: 10.13832/j.jnpe.2024.04.0045 |
[6] | Wang Ziming, Fu Junsen, Xiao Yao, Tian Xiaoyan, Su Chunlei, Li Da, Gu Hanyang. Study on Characteristics of Xi’an Pulsed Reactor in Reflood Stage[J]. Nuclear Power Engineering, 2024, 45(3): 60-67. doi: 10.13832/j.jnpe.2024.03.0060 |
[7] | Liu Luguo, Jiang Guangming, Xia Yunfeng, Liang Yu, Wang Mingjun, Liu Yu. Research on Multi-scale Coupling Simulation of Rod Bundle Channels Based on Subchannel-CFD Coupling Code[J]. Nuclear Power Engineering, 2024, 45(5): 256-261. doi: 10.13832/j.jnpe.2024.05.0256 |
[8] | Wang Suhao, Li Ying, Yue Nina, Guo Liang, Xiao Hui, Lou Ruifan, Zhuo Wenbin. Numerical Research on Anti-corrosion Properties of Rod Bundle Channel[J]. Nuclear Power Engineering, 2023, 44(S1): 88-94. doi: 10.13832/j.jnpe.2023.S1.0088 |
[9] | Yin Yuan, Feng Simin, Pang Bo, Xi Yanyan, Zhang Yuxiang, Fu Xiangang. Development of Dimensionless Rod-bundle CHF Correlation Based on Stepwise Regression and Determination of DNBR Limit[J]. Nuclear Power Engineering, 2023, 44(4): 72-78. doi: 10.13832/j.jnpe.2023.04.0072 |
[10] | Wang Jingjie, Zhu Dahuan, Lu Tao, Deng Jian, Cai Rong. Numerical Simulation of Turbulent Mixing of LBE between Sub-Channels of Wire-Wrapped Fuel Assembly[J]. Nuclear Power Engineering, 2021, 42(5): 30-35. doi: 10.13832/j.jnpe.2021.05.0030 |
[11] | Liu Wei, Peng Shinian, Jiang Guangming, Liu Yu. Development and Verification of a Comprehensive Rod Bundle CHF Mechanism Model[J]. Nuclear Power Engineering, 2021, 42(S2): 77-81. doi: 10.13832/j.jnpe.2021.S2.0077 |
[12] | Su Shu, Liu Chengmin, Huang Wei. Steady-State Thermal-Hydraulic Analysis of Steam Generator with Axial Economizer Based on Node Method[J]. Nuclear Power Engineering, 2021, 42(4): 39-44. doi: 10.13832/j.jnpe.2021.04.0039 |
[13] | Wen Yan, Liu Maolong. CFD Simulation of Quasi-Periodic Large Scale Vortices between Tight Lattice Subchannels[J]. Nuclear Power Engineering, 2020, 41(3): 41-44. doi: 10.13832/j.jnpe.2020.03.0041 |
[14] | Wang Ye, Sun Lanxin, Xu Changzhe, Hu Nan, Zheng Xu, Zhang Meng, Li Xiaochang. Numerical Study on Mixing Vane in Fuel Rod Bundle Channel of Nuclear Reactors[J]. Nuclear Power Engineering, 2019, 40(6): 54-58. doi: 10.13832/j.jnpe.2019.06.0054 |
[15] | Liu Da, Gu Hanyang. Experimental Study on Mixed Convection Heat Transfer in Rod Bundles[J]. Nuclear Power Engineering, 2018, 39(3): 13-17. doi: 10.13832/j.jnpe.2018.03.0013 |
[16] | Liu Yu, Tan Zhanglu, Pan Junjie, Wang Xiaoyu, Xu Liangjian, Deng Jian. Development of Self-reliant Subchannel Analysis Code CORTH[J]. Nuclear Power Engineering, 2017, 38(6): 157-162. doi: 10.13832/j.jnpe.2017.06.0157 |
[17] | Zhang Yuxiang, Xi Yanyan, Pang Zhengzheng, Li Weicai, Zhou Yuemin, Zhao Hua. CHF Correlation Development and DNBR Limits Determination[J]. Nuclear Power Engineering, 2016, 37(5): 130-134. doi: 10.13832/j.jnpe.2016.05.0130 |
[18] | Xiang Xiong, Shan Jianqiang, Zhang Bo. Development and Application of a Sub-Channel Analysis Code in Ocean Environment[J]. Nuclear Power Engineering, 2016, 37(1): 133-138. doi: 10.13832/j.jnpe.2016.01.0133 |
[19] | 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 |
[20] | CHEN Chao, DAN Jianqiang, ZHANG Bo. Sub-Channel Analysis of SCWR Assembly with Double-row Fuel Rods[J]. Nuclear Power Engineering, 2014, 35(2): 27-32. |