[1] | Shen Yong, Zeng Xiehu, Duan Zhengang, Wen Qinglong, Yuan Bo, He Liang, Gao Shixin. Investigation on Corrosion Model of Cr-coated Zirconium Alloy Cladding[J]. Nuclear Power Engineering, 2024, 45(S1): 175-180. doi: 10.13832/j.jnpe.2024.S1.0175 |
[2] | Song Xiaoyong, Pang Yongqiang, Meng Xiancai, Tian Shujian, Zhang Dehao, Li Xu. Design and Experimental Study of High Temperature Flowing Liquid Metal Corrosion Device[J]. Nuclear Power Engineering, 2024, 45(6): 263-270. doi: 10.13832/j.jnpe.2024.06.0263 |
[3] | 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 |
[4] | Lu Dingsheng, Wang Chen, Wang Chenglong, Yue Nina, Yang Ping, Tian Wenxi, Su Guanghui, Qiu Suizheng. Study on Oxidation Corrosion Characteristics of Horizontal Lead-Bismuth Reactor Core[J]. Nuclear Power Engineering, 2023, 44(3): 96-103. doi: 10.13832/j.jnpe.2023.03.0096 |
[5] | Wan Yi, Chen Zhihui, LI Yi, Xiao Kunjian, Lu Xin, He Ronghui, LI Chunmei. Device and Method for Nuclear Auxiliary Pump New Cavitation Test[J]. Nuclear Power Engineering, 2017, 38(S2): 84-86. doi: 10.13832/j.jnpe.2017.S2.0084 |
[6] | Chen Xuede, Liu Zicai, Zhang Kun, Lin Song, Li Pengzhou, Li Xihua. Research on Shock Stress Reduction Factor in Shock Stress Evaluation of Stainless Steel Piping[J]. Nuclear Power Engineering, 2016, 37(S2): 96-98. doi: 10.13832/j.jnpe.2016.S2.0096 |
[7] | Guo Xingkun, Tian Haowen, Zhou Yi, Zhang Minjie, Li Songling, Liu Songtao. Study on Corrosion and Hydriding Performance and Model of Specifically Fuel Rod Cladding[J]. Nuclear Power Engineering, 2016, 37(S1): 9-11. doi: 10.13832/j.jnpe.2016.S1.0009 |
[8] | Yang Zhang, Wang Hexu, Jiang Yanlong, Sun Chengbin. Diagnose and Treatment of Charging Pump Cavitation in Nuclear Power Stations[J]. Nuclear Power Engineering, 2016, 37(4): 77-80. doi: 10.13832/j.jnpe.2016.04.0077 |
[9] | Zeng Xiaokang, Zhou Huihui, Xiong Wanyu. CFD Study on Cavitation Abrasion for Axletree of Main Pump of Tianwan NPP[J]. Nuclear Power Engineering, 2016, 37(2): 143-146. doi: 10.13832/j.jnpe.2016.02.0143 |
[10] | He Chao, Lai Jiang, Yan Junming, Xi Zhide, Yuan Shaobo, Sun Lei. Research on Vibration Issue due to Pipe Orifice Cavitation[J]. Nuclear Power Engineering, 2016, 37(S2): 65-69. doi: 10.13832/j.jnpe.2016.S2.0065 |
[11] | Zhao Jingxiong, Liu Zhangliang. Analysis and Improvement of Throttling Orifice of NPP RCV System[J]. Nuclear Power Engineering, 2015, 36(4): 28-31. doi: 10.13832/j.jnpe.2015.04.0028 |
[12] | Xu Zhaoping. Experimental Analysis of RRA System Performance at Atmospheric Pressure[J]. Nuclear Power Engineering, 2015, 36(S1): 118-121. doi: 10.13832/j.jnpe.2015.S1.0118 |
[13] | Tian Haowen, Zhang Tengfei, Ceng Xiaokang. Mechanism Analysis and Improvement Measures for ThicknessReducing of Pipe behind Restriction Orifice in Deaerating System in Nuclear Power Plants[J]. Nuclear Power Engineering, 2015, 36(S1): 194-197. doi: 10.13832/j.jnpe.2015.S1.0194 |
[14] | FU Qiang, YUAN Shou-qi, ZHU Rong-sheng, WANG Tao, JIANG Xu-song. Cavitation Characteristics for Impeller of Centrifugal Charging Pump of M310 Nuclear Power Plants[J]. Nuclear Power Engineering, 2013, 34(6): 115-120. |
[15] | WANG Xiu-li, YUAN Shou-qi, ZHU Rong-sheng, YU Zhi-jun. Transient Flow Characteristics of Nuclear Reactor Coolant Pump in Recessive Cavitation Transition Process[J]. Nuclear Power Engineering, 2013, 34(3): 71-76. |
[16] | LI Qiang, HUANG Changjun, YANG Yanping, XU Long, LIANG Xue, ZHOU Bangxin. Nodular Corrosion Investigation of N18 Zirconium Alloys[J]. Nuclear Power Engineering, 2012, 33(S2): 22-27,38. |
[17] | HE Kun, SUN Danqi, ZHANG Hai, LIU Gang. Study on Dynamic Corrosion Performance of Stainless Steel Used as Primary Pipe[J]. Nuclear Power Engineering, 2012, 33(S2): 83-86. |
[18] | WANG Xiuli, YUAN Shouqi, ZHU Rongsheng, YU Zhijun. Numerical Analysis for Causes of Cavitation Fracture Working Condition on Centrifugal Pump[J]. Nuclear Power Engineering, 2012, 33(6): 101-104,114. |
[19] | WANG Guili, MA Na, CHEN Yong. Difference between Flow Accelerated Corrosion and Erosion-Corrosion of Carbon Steel Pipes[J]. Nuclear Power Engineering, 2012, 33(S2): 75-78. |
[20] | KANG Huan-ju, YANG Shuang, SUN Hua. Experimental Study on Stress Corrosion Cracking of 316LN[J]. Nuclear Power Engineering, 2011, 32(6): 101-104,114. |