[1] | Yan Meng, Li Shunping, Wang Pengfei, Hong Xiaofeng, Liang Bo, Dai Xun, Yin Qiwei. Research on Hoop Mechanical Property of Zr-Sn-Nb Alloy Cladding Tubes in Vacuum[J]. Nuclear Power Engineering, 2023, 44(3): 127-131. doi: 10.13832/j.jnpe.2023.03.0127 |
[2] | Zhang Xiaowei, Zhou Bin, Niu Haoxuan, Yu Yang. The Study on Seismic Analysis and Test Method of Nuclear Grade Fan[J]. Nuclear Power Engineering, 2023, 44(3): 132-137. doi: 10.13832/j.jnpe.2023.03.0132 |
[3] | Wang Zhanwei, Yan Jun, Peng Zhenxun, Ren Qisen, Liao Yehong, Li Sigong, Zhao Yahuan. Experimental Study of Cr-coated Zirconium Alloy Cladding under Simulated LOCA Conditions[J]. Nuclear Power Engineering, 2023, 44(2): 122-128. doi: 10.13832/j.jnpe.2023.02.0122 |
[4] | Qi Yanqiang, Li Shunping, Peng Qian, Yan Meng, Chen Le, Dai Xun. Study on Low-cycle Fatigue Test Method for Zr-Sn-Nb Alloy Welded Sheets[J]. Nuclear Power Engineering, 2023, 44(S1): 188-193. doi: 10.13832/j.jnpe.2023.S1.0188 |
[5] | Li Pengzhou, Li Yilei, Sun Lei, Qiao Hongwei, Chen Xuede, Zhang Kun, Li Xihua. Research on Anti-Impact Scaling Test Method for Supporting Structure of Large Equipment[J]. Nuclear Power Engineering, 2022, 43(4): 99-105. doi: 10.13832/j.jnpe.2022.04.0099 |
[6] | Ren Quan yao, Pu Zeng ping, Jiao Yongjun, Zheng Meiyin, Chen Ping, Han Yuanji, Liu Menglong, Zhuang Wenhua, Guo Xianglong, Zhang Lefu. Study on Tangential Fretting Wear Behavior of Zirconium Alloy Cladding at High Temperature[J]. Nuclear Power Engineering, 2022, 43(S2): 82-87. doi: 10.13832/j.jnpe.2022.S2.0082 |
[7] | Zhang Weichuan, Zhao Hui, Qin Fan, Zhao Yang, Qing Xianguo, Chen Jie, He Xiaopeng. Application of HALT Test Method in Development of Digital Instrument and Control Equipment[J]. Nuclear Power Engineering, 2021, 42(S2): 99-103. doi: 10.13832/j.jnpe.2021.S2.0099 |
[8] | Sun Yugang, Chu Meng, Ding Zhenkun, Yuan Fang. Analysis of Inspection Methods for Power Spectral Density in Seismic Qualification Test of Equipment in Nuclear Power Plants[J]. Nuclear Power Engineering, 2020, 41(4): 101-104. |
[9] | Yuan Meichun, Sun Dongmei, Nan Xiayu. Research and Application of Calibration Test Method for PTR Liquid Level Gauge in EPR Units[J]. Nuclear Power Engineering, 2020, 41(5): 168-172. |
[10] | Li Zhiming, Wang Hongqing, Ma Weigang, Qiu Tian, Li Yang, Jiang E. Investigation on Experimental Method for Validating Performance of Passive Autocatalytic Hydrogen Recombiner[J]. Nuclear Power Engineering, 2019, 40(3): 138-141. doi: 10.13832/j.jnpe.2019.03.0138 |
[11] | Liu Zhen, Yang Si, Wang Chenghan. Optimization of Method for Finding Doppler Heating Starting Point in Qinshan Nuclear Power Plant Ⅱ[J]. Nuclear Power Engineering, 2018, 39(1): 17-19. doi: 10.13832/j.jnpe.2018.01.0017 |
[12] | Luo Xuzhen, Wang Jian, HE Ziang, Liu Xiaorong, Yuan Jun, Yuan Qunqi. Research on Depth Control Process of Titanium Alloy Tube Sheet Weld by Electron Beam Welding[J]. Nuclear Power Engineering, 2017, 38(3): 47-50. doi: 10.13832/j.jnpe.2017.03.0047 |
[13] | Chen Le, Yang Zhongbo, Qiu Jun, Liang Bo, Li Weijun, Hong Xiaofeng, Wang Lian. Effect of Heat Treatment on Tensile Properties and Microstructure of New Domestic Zirconium Alloys[J]. Nuclear Power Engineering, 2017, 38(6): 129-133. doi: 10.13832/j.jnpe.2017.06.0129 |
[14] | Dai Xun, Wang Pengfei, Wang Ying, Cheng Zhuqing, Yang Zhongbo, Zhao Wenjin, Zhuo Hong. Study on Second Phase Particles in N36 Alloy Claddings and Bars[J]. Nuclear Power Engineering, 2017, 38(S1): 13-17. doi: 10.13832/j.jnpe.2017.S1.0013 |
[15] | Yan Meng, Wang Pengfei, Hong Xiaofeng, Liang Bo, DAi Xun. Evaluation on I-SCC Properties of Zirconium Cladding[J]. Nuclear Power Engineering, 2017, 38(5): 138-140. doi: 10.13832/j.jnpe.2017.05.0138 |
[16] | Peng Jinfeng, Xu Jianjun, Huang Yanping, Liu Wenxing, Huang Hongwen, Peng Shuming. Experimental Research of Critical Heat Flux under Uniform Heating and Circumferential Nonuniform Heating in Vertical Circular Channel[J]. Nuclear Power Engineering, 2016, 37(1): 38-42. doi: 10.13832/j.jnpe.2016.01.0038 |
[17] | Li Qi, Li Pengzhou, Du Jianyong, Li Tianyong, Sun Lei, Li Pengfei. Exploration of Seismic Qualification Test Method for Nuclear Safety Class Valves[J]. Nuclear Power Engineering, 2016, 37(S2): 58-61. doi: 10.13832/j.jnpe.2016.S2.0058 |
[18] | YAN Meng, WANG Pengfei, LIANG Bo, HONG Xiaofeng. Iodine Induced Stress Corrosion Cracking of N36 Zirconium Tube in Hoop Tensile Condition[J]. Nuclear Power Engineering, 2015, 36(1): 46-49. doi: 10.13832/j.jnpe.2015.01.0046 |
[19] | ZHU Haiyan, YAN Xiao, ZENG Xiaokang, LI Yongliang, HUANG Yanping, XIAO Zejun. Analysis on Circumferential Non-Uniformity in Heat Transfer Behavior of Supercritical Water in Smooth Square Annular Channel[J]. Nuclear Power Engineering, 2012, 33(5): 54-58. |
[20] | YAN Meng, PENG Qian, ZHAO Wenjin, SHENG Zhongqi, DAI Xun. Fracture Morphology Analysis of Iodine Induced Stress Corrosion Cracking of N36 Zirconium Tube[J]. Nuclear Power Engineering, 2012, 33(S2): 47-50. |