[1] | Tan Sichao, Wei Tianyi, Yu Xiaoyong, Xie Guanhui, Li Xupeng, Tian Ruifeng. PLIF Technology and Its Application in Researches of Nuclear Reactor Thermal-hydraulics[J]. Nuclear Power Engineering, 2024, 45(1): 1-10. doi: 10.13832/j.jnpe.2024.01.0001 |
[2] | Yuan Pan, Wang Haoyu, Huang Shan, Liu Menglong, Yue Ti, Ren Quanyao, Qin Mian, Zheng Lele, Guo Zixuan. Research on Thermal-fluid-structure Coupling Behavior for U-10Mo/Al Fuel Assemblies under Irradiation[J]. Nuclear Power Engineering, 2023, 44(S2): 11-16. doi: 10.13832/j.jnpe.2023.S2.0011 |
[3] | Wang Zhe, Zhang Dan, Zou Zhiqiang, Wang Ningning, Yang Weidong, Du Yu. Probabilistic Safety Analysis Framework for Internal Events of Aqueous Homogeneous Reactor[J]. Nuclear Power Engineering, 2023, 44(4): 133-137. doi: 10.13832/j.jnpe.2023.04.0133 |
[4] | Zhao Xuebin, Huang Yanping, Zang Jinguang. Research and Development on Thermal Hydraulic and Safety of Supercritical Water-cooled Reactor[J]. Nuclear Power Engineering, 2023, 44(5): 223-231. doi: 10.13832/j.jnpe.2023.05.0223 |
[5] | Zhang Xinyi, Wang Lipeng, Wang Yongping, Jiang Xinbiao, Yin Huabei, He Bin, Li Da, Zhang Liang, Jiang Duoyu, Hu Tianliang. Influence of Depletion on Reactivity Insertion Transients for Xi’an Pulsed Reactor[J]. Nuclear Power Engineering, 2023, 44(5): 30-38. doi: 10.13832/j.jnpe.2023.05.0030 |
[6] | Zhang Liang, Yang Wenhua, Zhao Wenbin, Sun Sheng, Jin Shuai, Lei Jin. Design and Analysis of Irradiation Test Scheme for Fast Reactor Fuel Slug with HFETR[J]. Nuclear Power Engineering, 2022, 43(3): 101-106. doi: 10.13832/j.jnpe.2022.03.0101 |
[7] | Zhang Wei, Li Jingsong, Shi Huilie, Qiao Pengrui, Wang Cong, Zhang Tianqing, He Yingzhao. Thermal-Hydraulic Performance Analysis of Horizontal Spiral Tube Steam Generator for European Lead-Cooled Fast Reactor[J]. Nuclear Power Engineering, 2022, 43(3): 38-45. doi: 10.13832/j.jnpe.2022.03.0038 |
[8] | Ding Xueyou, Chen Zhiqiang, Wen Qinglong, Ruan Shenhui, Qiao Pengrui. Numerical Investigation on Thermal Hydraulics of Helical Coil Tube Once Through Steam Generator for LBE Fast Reactor[J]. Nuclear Power Engineering, 2021, 42(4): 21-26. doi: 10.13832/j.jnpe.2021.04.0021 |
[9] | Chen Hongsheng, Long Chongsheng, Xiao Hongxing, Wei Tianguo, Gao Wen. Releasing Model of Fission Gas Based on Dispersion Fuel Particle Cracking[J]. Nuclear Power Engineering, 2019, 40(5): 85-91. |
[10] | Liu Wei, Zhang Yong, Jiang Xiaowei, Zhang Cheng, Zhang Dalin. Development and Verification of Thermal-Hydraulic Transient Analysis Code in Plate-Type Fuel Nuclear Reactor[J]. Nuclear Power Engineering, 2019, 40(5): 18-22. |
[11] | Wei Shiying, Wang Chenglong, Su Guanghui, Tian Wenxi, Qiu Suizheng. Development of Analysis Code for Pb-Bi Cooled Direct-Contact-Boiling Water Fast Reactor System[J]. Nuclear Power Engineering, 2018, 39(4): 67-70. doi: 10.13832/j.jnpe.2018.04.0067 |
[12] | Qu Shen, Cao Liangzhi, Zhou Shengcheng, Liu Hangang. Study on Depletion Calculation of Heat Pipe Cooled Space Reactor[J]. Nuclear Power Engineering, 2018, 39(5): 4-8. doi: 10.13832/j.jnpe.2018.05.0004 |
[13] | Peng Yu, Zou Yang, Dai Ye, Xu Hongjie, Zhu Guifeng. Research on Coupling of Neutronics and Thermal-Hydraulics for Solid Fuel Molten Salt Reactor[J]. Nuclear Power Engineering, 2017, 38(2): 1-5. doi: 10.13832/j.jnpe.2017.02.0001 |
[14] | Liu Tingting, Lin Xusheng, Yang Senquan, Xie Zhengquan, Luo Fanghui. Study and Verification of Burnup Calculation Strategy in Lattice Physics Code SimFA[J]. Nuclear Power Engineering, 2014, 35(S2): 155-158. doi: 10.13832/j.jnpe.2014.S2.0155 |
[15] | Zhang Mao, He Chaoming, Cheng Peipei. Design of Automatic Measurement System for Plate-Type Fuel Element Burn-up[J]. Nuclear Power Engineering, 2014, 35(6): 100-105. doi: 10.13832/j.jnpe.2014.06.0100 |
[16] | SUI Zhe, ZHANG Rui-peng, SUN Jun, MA Yuan-le. Real Time Thermal Hydraulic Model for High Temperature Gas-cooled Reactor Core[J]. Nuclear Power Engineering, 2013, 34(2): 20-24. |
[17] | TANG Huapeng, YAN Mingyu, LU Chuan, FENG Linna, CHEN Bin, LIANG Tao. Study on CANDLE Burnup Concept[J]. Nuclear Power Engineering, 2013, 34(S1): 221-224. |
[18] | ZENG Xiao-kang, LI Yong-liang, YAN Xiao, XIAO Ze-jun, HUANG Yan-ping. Application of CFD Methods in Research of SCWR Thermo-Hydraulics[J]. Nuclear Power Engineering, 2013, 34(1): 114-120. |
[19] | SHI Xueming, PENG Xianjue. Effect of Volume Ratio between Uranium and Water on Fusion-Fission Hybrid for Energy Production[J]. Nuclear Power Engineering, 2012, 33(4): 139-142. |
[20] | WANG Liangzi, YAO Dong, WANG Kan. Burn-up Function of Fuel Management Code for Aqueous Homogeneous Reactors and Its Validation[J]. Nuclear Power Engineering, 2011, 32(4): 127-130,142. |