[1] | Wang Xiaohu, Zhao Pinghui, Ye Taohong, Xiong Yan, Tan Chao, Chen Yunlong. Research on Correction Method of Pressure Spike at Gas-Liquid Interface Crossing Cells Based on RELAP5[J]. Nuclear Power Engineering, 2024, 45(1): 34-40. doi: 10.13832/j.jnpe.2024.01.0034 |
[2] | Xu Rongshuan, Xia Hang, Xu Caihong, He Dongyu, Wang Ting, Li Jinggang. Verification and Uncertainty Evaluation of LOCUST Reflood Model[J]. Nuclear Power Engineering, 2024, 45(4): 111-117. doi: 10.13832/j.jnpe.2024.04.0111 |
[3] | Zhao Wei, Chen Lixin, Liu Guodong, Zhang Liang, Yang Ning, Zhang Xinyi, Tian Xiaoyan, Sun Peiwei, Yuan Jianxin. Multi-scale Coupling Transient Characteristics of Xi 'an Pulsed Reactor Based on RELAP5 and CTF[J]. Nuclear Power Engineering, 2023, 44(3): 59-64. doi: 10.13832/j.jnpe.2023.03.0059 |
[4] | Li Xiang, Sun Wan, Ding Shuhua, Huang Tao, Li Zhongchun, Pan Liangming. Study on CCFL Characteristics in Downcomer during Discharge Phase of LOCA with RELAP5 Code[J]. Nuclear Power Engineering, 2022, 43(3): 58-65. doi: 10.13832/j.jnpe.2022.03.0058 |
[5] | Zeng Wei, Wang Jie, Huang Tao, Chen Wei, Ding Shuhua, Deng Chengcheng, Yang Jun. Study on Important Phenomenon Identification and Numerical Simulation Uncertainty Analysis for PWR Large Break LOCA[J]. Nuclear Power Engineering, 2021, 42(1): 198-203. doi: 10.13832/j.jnpe.2021.01.0198 |
[6] | Zhao Ningning, Yuan Hongsheng, Wen Qinglong, Ruan Shenhui. Evaluation of the Impact of Core Power Distribution on Reflooding Phenomenon in CCTF Test[J]. Nuclear Power Engineering, 2021, 42(6): 58-64. doi: 10.13832/j.jnpe.2021.06.0058 |
[7] | Liu Yusheng, Xu Chao, Hu Jian, Zhuang Shaoxin, Fang Fangfang. Numerical Analysis of ACME Station Blackout Integral Effect Test with Relap[J]. Nuclear Power Engineering, 2019, 40(3): 98-102. doi: 10.13832/j.jnpe.2019.03.0097 |
[8] | Xian Lin, Jiang Guangming, Li Jie, Wang Xiaoji, Yang Fan, Li Feng, Ran Xu. Improvement and Validation of Free Convection Heat Transfer Model for Tube Bundle in RELAP5[J]. Nuclear Power Engineering, 2018, 39(3): 29-32. doi: 10.13832/j.jnpe.2018.03.0029 |
[9] | Liang Weihong, Xie Heng. Analyses on Flow Instability of Secondary-Side Passive Residual Heat Removal System for Advanced Nuclear Heating Reactor[J]. Nuclear Power Engineering, 2018, 39(2): 14-19. doi: 10.13832/j.jnpe.2018.02.0014 |
[10] | Li Haitao, Zhou Chunlin, Zou Deguang, Zhang Jiangyun, Wang Wenlong, Xiao Dun, Jiang Tinglan. RELAP5 Model and Test Evaluation of High Flux Engineering Test Reactor[J]. Nuclear Power Engineering, 2018, 39(S2): 112-115. doi: 10.13832/j.jnpe.2018.S2.0112 |
[11] | Wang Chenglong, Hu Lingwen, Qiu Suizheng, Su Guanghui, Tian Wenxi. Uncertainty Analysis of Transportable Fluoride-Salt-Cooled High Temperature Reactor(TFHR)[J]. Nuclear Power Engineering, 2017, 38(3): 168-171. doi: 10.13832/j.jnpe.2017.03.0168 |
[12] | Gong Houjun, Xi Zhao, Zan Yuanfeng, Zhuo Wenbin, Huang Yanping. Sensitivity Study on Secondary Side Passive Residual Heat Removal System Based on RELAP5[J]. Nuclear Power Engineering, 2016, 37(6): 11-14. doi: 10.13832/j.jnpe.2016.06.0011 |
[13] | Hao Chen, Zhao Qiang, Li Fu, Yu Yan, Zhang Chunyan, Zhang Huiyan. Uncertainty Analysis of Advanced Pressurized Water Reactor Fuel Assembly[J]. Nuclear Power Engineering, 2016, 37(3): 173-180. doi: 10.13832/j.jnpe.2016.03.0173 |
[14] | Fang Jun, Wu Nan, Qi Ting. Applicability Research of RELAP5 for Steam Generator Tube Rupture Accident of AP1000 NPP[J]. Nuclear Power Engineering, 2016, 37(3): 70-74. doi: 10.13832/j.jnpe.2016.03.0070 |
[15] | Shi Chengbin, Cheng Maosong, Liu Guimin. Extending and Verification of RELAP5 Code for Liquid Fueled Molten Salt Reactor[J]. Nuclear Power Engineering, 2016, 37(3): 16-20. doi: 10.13832/j.jnpe.2016.03.0016 |
[16] | Xiong Wanyu, Gong Houjun, Xi Zhao, Zhuo Wenbin, Huang Yanping. Preliminary Evaluation of RELAP5 for Design of Secondary Side Passive Residual Heat Removal System[J]. Nuclear Power Engineering, 2015, 36(2): 143-146. doi: 10.13832/j.jnpe.2015.02.0143 |
[17] | LÜ Li, Yu Tao, Yu Hongxing, Wu Dan, Xie Jinsen, Peng Huanhuan. Research on Wall-to-Vapor Convective Heat Transfer Model in Reflooding Phase of Typical PWR Based on RELAP5[J]. Nuclear Power Engineering, 2015, 36(2): 42-45. doi: 10.13832/j.jnpe.2015.02.0042 |
[18] | Li Dong, Xu Wei, Liu Xiaojing, Yang Yanhua. Improvement of RELAP5 Models Related to Reflood Phenomenon Based on Sensitivity Analysis[J]. Nuclear Power Engineering, 2015, 36(S2): 151-156. doi: 10.13832/j.jnpe.2015.S2.0151 |
[19] | ZENG Wei, ZHU Li, LIU Song-tao, YU Hong-xing, SUN Yu-fa. Research on Effect of Two-Phase Interfacial Friction Characteristics on Quench Front Velocity in Narrow Channel[J]. Nuclear Power Engineering, 2013, 34(6): 66-69,74. |
[20] | ZENG Wei, YU Hong-xing, SUN Yu-fa, LI Feng. Research on Reflood Model of Narrow Channel Based on RELAP5[J]. Nuclear Power Engineering, 2013, 34(3): 50-57. |