[1] | Huang Jun, Ying Bingbin, Zheng Mingguang. Flow Field and Blowdown Test of Secondary Side Lower Part of Steam Generator[J]. Nuclear Power Engineering, 2024, 45(2): 193-198. doi: 10.13832/j.jnpe.2024.02.0193 |
[2] | Zheng Junwei, Liu Hang, Li Wenhai, Liu Jikun. Study and Verification of Diagnosis Method for Secondary Neutron Source Breakage[J]. Nuclear Power Engineering, 2023, 44(1): 167-170. doi: 10.13832/j.jnpe.2023.01.0167 |
[3] | Xian Lin, Li Feng, Yu Na, Wu Qing, Qiu Zhifang, Deng Jian, Lu Yili, Li Haiying. Improvement and Analysis of Design of Secondary-side Passive Residual Heat Removal System for PWR[J]. Nuclear Power Engineering, 2023, 44(3): 160-164. doi: 10.13832/j.jnpe.2023.03.0160 |
[4] | Zhang Dong, Zhang Haochun, Wang Qi, Sun Wenbo. Thermal-Hydraulic Investigation of LBE Cooled Wire-Wrapped Fuel Bundle Based on Entropy Generation Analysis[J]. Nuclear Power Engineering, 2022, 43(S2): 125-130. doi: 10.13832/j.jnpe.2022.S2.0125 |
[5] | Liu Fayu, Zhang Xiaoying, Chen Jiayue, Chen Hu, ong. Analysis of Coupled Flow and Heat Transfer in Primary and Secondary Sides of Helical Coil Once-Through Tube Steam Generator[J]. Nuclear Power Engineering, 2020, 41(5): 24-29. |
[6] | Zhou Biao, Ji Yu, Sun Jun, Sun Yuliang, Shi Lei. Numerical Investigations of Supercritical Hydrogen Flow and Heat Transfer in Curved Tube[J]. Nuclear Power Engineering, 2019, 40(5): 197-201. |
[7] | Dou Haifeng, Li Rundong, Zhu Shilei, Wang Junwei, Si Kaituo, Yuan Shu, Yang Xin, Leng Jun. Determination of Fissile Nuclide 235U Content in Re-Irradiated Spent Fuel Assemble with Nondestructive Assay[J]. Nuclear Power Engineering, 2018, 39(3): 51-55. doi: 10.13832/j.jnpe.2018.03.0051 |
[8] | Xi Zhao, XiE Feng, Gong Houjun, Yu Shimo, SuN Doucheng, Xiong Wanyu, Zan Yuanfeng. Experimental Research on the Parameter Affecting on the Characteristics of Secondary Side Residual Heat Removal System[J]. Nuclear Power Engineering, 2017, 38(6): 5-8. doi: 10.13832/j.jnpe.2017.06.0005 |
[9] | Xi Zhao, Sun Doucheng, Zhu Yuan, XiE Feng, Li Yong, Zan Yuanfeng, Zhuo Wenbin. Experimental Research of Natural Circulation Characteristics in Secondary Side Passive Residual Heat Removal System[J]. Nuclear Power Engineering, 2017, 38(5): 10-13. doi: 10.13832/j.jnpe.2017.05.0010 |
[10] | Wang Cong, Lu Daogang, Yao Zhipeng, Cao Qiong, Awais Ahmad, Zhang Shuming. PIV Experiment Research on Flow Pattern in Secondary Side of Steam Generator Based on a Visible Experimental Facility[J]. Nuclear Power Engineering, 2017, 38(5): 4-9. doi: 10.13832/j.jnpe.2017.05.0004 |
[11] | Zhou Yangping, Hao Pengfei, Li Fu, Shi Lei, He Feng. Investigation on Numerical Simulation for Hot Gas Mixing Structure of HTR-PM by Considering Leakage Flow[J]. Nuclear Power Engineering, 2016, 37(3): 169-172. doi: 10.13832/j.jnpe.2016.03.0169 |
[12] | Xi Zhao, Xiong Wanyu, Xie Feng, Gong Houjun, Zhuo Wenbin, Li Pengzhou. Experimental Study on Natural Circulation Characteristics of Passive Residual Heat Removal System[J]. Nuclear Power Engineering, 2015, 36(4): 1-3. doi: 10.13832/j.jnpe.2015.04.0001 |
[13] | He Gening, He Jingsong, Li Donghui, Wu Ge, Huo Meng. Flow Analysis and Structure Optimization of Electric Heating Tank of Steam Generator Secondary Side Pre-Service Hydrostatic Test System[J]. Nuclear Power Engineering, 2015, 36(S2): 46-49. doi: 10.13832/j.jnpe.2015.S2.0046 |
[14] | Liu Junfeng, Li Kang, Ma Xiaolong. Research on Blowing Technology for Secondary Side in HTR-PM Steam Generator[J]. Nuclear Power Engineering, 2015, 36(3): 117-119. doi: 10.13832/j.jnpe.2015.03.0117 |
[15] | JinG Futing, Xiao Feng, Liu Jiajia, Tan Yi, Lyu Huanwen. Calculation of Neutron Source Strength from Secondary Neutron Source in PWRs[J]. Nuclear Power Engineering, 2014, 35(S2): 64-66. doi: 10.13832/j.jnpe.2014.S2.0064 |
[16] | CONG Tenglong, TIAN Wenxi, QIU Suizheng, SU Guanghui, XIE Yongcheng, YAO Yangui. Three-Dimensional Steady Calculation on Two-Phase Flow in Secondary Side of Steam Generator[J]. Nuclear Power Engineering, 2014, 35(2): 37-40. |
[17] | ZHOU Lei, YAN Xiao, XI Zhao, XIONG Wan-yu, XIAO Zejun. Investigation on Scaling Criteria of Secondary Side Passive Residual Heat Removal System[J]. Nuclear Power Engineering, 2012, 33(S1): 32-36,94. |
[18] | AN Run. Research on Number of Insoluble Impurities from Second Side of Steam Generator[J]. Nuclear Power Engineering, 2012, 33(5): 133-135. |
[19] | LEI Xianliang, LI Huixiong, YU Shuiqing. Numerical Simulation of Heat Transfer and Mixing Characteristics of Supercritical Pressure Water in Horizontal Tubes in Large Specific Heat Region[J]. Nuclear Power Engineering, 2012, 33(1): 29-33,38. |
[20] | QIAN Hao, XIE Yong-cheng, ZHANG Ke-feng. Preliminary Analysis of Flow Induced Vibration for AP1000 Secondary Core Support Assembly[J]. Nuclear Power Engineering, 2011, 32(S1): 145-148,158. |