[1] | Wang Xinan, Zhang Dalin, Wang Ting, Qiu Suizheng, Su Guanghui. A Porous Media Model for Thermal-hydraulic Analysis of Wire-wrapped Fuel Assembly in Sodium Cooled Fast Reactor[J]. Nuclear Power Engineering, 2024, 45(2): 147-153. doi: 10.13832/j.jnpe.2024.02.0147 |
[2] | Peng Xinhang, Zhang Tian, Shao Shihao, Liu Zhouyu. Verification of Sodium-cooled Fast Reactor SUPERFACT-1 SF4/SF16 Fuel Rod Experiment using LoongCALF Code[J]. Nuclear Power Engineering, 2024, 45(S1): 117-122. doi: 10.13832/j.jnpe.2024.S1.0117 |
[3] | Liu Yapeng, Zhang Dalin, Chen Yutong, Zhou Lei, Tian Wenxi, Qiu Suizheng, Su Guanghui. Numerical Simulation of the Natural Circulation Test of PHENIX Reactor by ACENA[J]. Nuclear Power Engineering, 2024, 45(5): 121-127. doi: 10.13832/j.jnpe.2024.05.0121 |
[4] | Qiu Zhifang, Guo Rongda, Cao Xuewu, Yu Hongxing, Sun Hongping, Luo Yuejian. Experimental and Numerical Simulation Study on Pressure Suppression Characteristics of Small PWR[J]. Nuclear Power Engineering, 2023, 44(1): 60-66. doi: 10.13832/j.jnpe.2023.01.0060 |
[5] | Guo Xiaoxian, Gu Jipin, Zhu Hao, Liu Yang, Li Taifeng, Zhang Hu. Study on the Operation Characteristics of the Primary Main Circulating Pump of Sodium-cooled Fast Reactor under the Switching Condition of Off-site Main and Auxiliary Power Supplies[J]. Nuclear Power Engineering, 2023, 44(1): 104-108. doi: 10.13832/j.jnpe.2023.01.0104 |
[6] | Dai Raoqi, Duan Tianying, Liu Yong, Zhang Houming, Zhang Weiying, Xu Weidong. Analysis of Load-following Operation Capability of Large Sodium-cooled Fast Reactor[J]. Nuclear Power Engineering, 2023, 44(6): 199-205. doi: 10.13832/j.jnpe.2023.06.0199 |
[7] | Zhang Zekai, Zhang Tingting, Yin Shasha, Yin Junlian, Wang Dezhong. Numerical Simulation of Gas-liquid Two-phase Separation in Vortex Separator[J]. Nuclear Power Engineering, 2022, 43(6): 201-208. doi: 10.13832/j.jnpe.2022.06.0201 |
[8] | Zhang Rui, Wu Qi, Ma Zaiyong, Chu Tao, Zhang Luteng, Tang Yu, Sun Wan, Pan Liangming. Numerical Simulation of Reverse Flow in Inverted U-tube Steam Generator under Low Flow Single-phase Condition[J]. Nuclear Power Engineering, 2022, 43(S2): 33-39. doi: 10.13832/j.jnpe.2022.S2.0033 |
[9] | Li Rupeng, Ye Cheng, Qi Lian, Du Liguo, Huang Jiayun. Study on Reactor-Mechanical-Electricity for Capacity Expansion and Retrofitting of 320 MWe Steam Turbine Generator Unit in Qinshan Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(S1): 75-79. doi: 10.13832/j.jnpe.2022.S1.0075 |
[10] | Wang Cong, Zhang Wei, Li Jingsong, Qiao Pengrui, Shi Huilie. A Method Study of Numerical Simulation on Flow Field of Spiral Tube in Steam Generator Shell Side[J]. Nuclear Power Engineering, 2021, 42(4): 171-175. doi: 10.13832/j.jnpe.2021.04.0171 |
[11] | Teng Chunming, Zhang Bin, Shan Jianqiang, Zhang Xisi, Cao Yonggang. Applicability Analysis of Onset Model for Debris Bed Relocation in Sodium-Cooled Fast Reactor[J]. Nuclear Power Engineering, 2021, 42(1): 42-47. doi: 10.13832/j.jnpe.2021.01.0042 |
[12] | Xu Weidong, Duan Tianying, Fu Hao, Feng Weiwei, Yang Peng. Research on Shutdown Protection Scheme for Sodium Cooled Fast Reactor[J]. Nuclear Power Engineering, 2021, 42(1): 54-60. doi: 10.13832/j.jnpe.2021.01.0054 |
[13] | Teng Chunming, Zhang Bin, Shan Jianqiang, Zhang Xisi, Cao Yonggang. Experimental Study of Debris Bed Relocation in Sodium-Cooled Fast Reactor by Bottom Gas-Injection Method[J]. Nuclear Power Engineering, 2020, 41(4): 141-147. |
[14] | Huang Qian, Yu Xiaofei, Qi Huanhuan, Feng Zhipeng, Jiang Naibin, Song Haiyang. Numerical Analysis of Dynamic Response for SG LOCA Shaking[J]. Nuclear Power Engineering, 2019, 40(1): 82-86. doi: 10.13832/j.jnpe.2019.01.0082 |
[15] | Sui Zengguang, Yang Jun, Yang Ye, Dong Shichang, Xu Lejin. Simulation of Reflux in U-Tube of Steam Generator Based on CFD Method[J]. Nuclear Power Engineering, 2019, 40(2): 10-15. doi: 10.13832/j.jnpe.2019.02.0010 |
[16] | Cao Simin, Huang Wei, Yang Ming. Numerical Simulation of Thermal Striping in Pressurizer Surge Line[J]. Nuclear Power Engineering, 2017, 38(S2): 55-59. doi: 10.13832/j.jnpe.2017.S2.0055 |
[17] | Fu Guanhua, Li Quanbing, Ren Hongbing, Zhou Peng, Duan Yuangang. Simulation Research on PZR Water Seal of Nuclear Power Plants[J]. Nuclear Power Engineering, 2017, 38(5): 40-44. doi: 10.13832/j.jnpe.2017.05.0040 |
[18] | HUANG Zheng. Simulation of Steam Condensation Inside Vertical Tube with Noncondensable Gases Using MELCOR[J]. Nuclear Power Engineering, 2015, 36(1): 127-131. doi: 10.13832/j.jnpe.2015.01.0127 |
[19] | ZHANG Shi, WANG De-zhong, MA Yuan-wei. Numerical Simulation of Steam Migration in Containment of Large-Sized Advanced PWRs[J]. Nuclear Power Engineering, 2013, 34(2): 30-33. |
[20] | ZUO Qiaolin, QIU Suizheng, LU Wei, SU Guanghui, TIAN Wenxi, WANG Sheng, XIAO Zejun. Numerical Simulation of Water Hammer Characteristics for Integral Reactor Primary Circuit[J]. Nuclear Power Engineering, 2012, 33(4): 85-90. |