[1] | Zhang Lefu, Huang Tao, Su Haozhan, Gao Yang, Guo Xianglong, Shen Zhao, Chen Kai. Progress and Considerations on Candidate Cladding Materials for Supercritical Water-Cooled Reactors[J]. Nuclear Power Engineering, 2025, 46(1): 183-190. doi: 10.13832/j.jnpe.2025.01.0183 |
[2] | Liu Zhenshun, Zhang Sheng, Mao Qing, Zheng Xiangyuan. Research on the Closure Effect of Circumferential Through-Wall Cracks in Stainless Steel Piping under Residual Stress[J]. Nuclear Power Engineering, 2023, 44(2): 152-158. doi: 10.13832/j.jnpe.2023.02.0152 |
[3] | Zhao Yuxiang, Xiong Ru, Liang Bo, Tang Rui. Experimental Study on Low-Cycle Fatigue Properties of Supercritical Water-cooled Reactor Candidate Cladding Material[J]. Nuclear Power Engineering, 2023, 44(5): 237-243. doi: 10.13832/j.jnpe.2023.05.0237 |
[4] | Song Danrong, Xu Bin, Liu Jia, Qin Dong, Zhang Xianjun, Wang Zhuo, Zhu Hong. Design and Research of Data Management System for the Whole Life Cycle of Small Modular Reactor Structural Materials[J]. Nuclear Power Engineering, 2022, 43(5): 119-125. doi: 10.13832/j.jnpe.2022.05.0119 |
[5] | Su Haozhan, Wang Peng, Zhang Lefu. Effect of Working Medium Pressure and Creep on the Stress Corrosion Cracking Behavior of Cold Deformed 310S Stainless Steel in Supercritical Water Environment[J]. Nuclear Power Engineering, 2022, 43(6): 108-116. doi: 10.13832/j.jnpe.2022.06.0108 |
[6] | Yuan Xudong, Ma Huiqiang, Chen Zhenping, Guo Shuwei, Xie Jinsen, Yang Chao, Yu Tao. Study on Activation-Induced Dose Calculation of Reactor Structural Materials[J]. Nuclear Power Engineering, 2021, 42(5): 103-109. doi: 10.13832/j.jnpe.2021.05.0103 |
[7] | Su Haozhan, Chen Kai, Zhang Lefu, Dang Ying, Chen Le. Investigation on Corrosion Fatigue Behavior of 316LN SS under High Temperature Water Environment[J]. Nuclear Power Engineering, 2020, 41(1): 37-42. doi: 10.13832/j.jnpe.2020.01.0037 |
[8] | Zhao Yuxiang, Liu Ranchao, He Kun, Xiong Ru, Wang Li. Study on High-Cycle Fatigue Behavior for TA16 and 690 Tube[J]. Nuclear Power Engineering, 2017, 38(5): 129-131. doi: 10.13832/j.jnpe.2017.05.0129 |
[9] | Si Junping, Tong Mingyan, Yang Wenhua, Zhang Liang, Nie Liangbing, Zhang Ping. Measurement and Calculation of Heat Generation Rate of Stainless Steel in a Research Reactor[J]. Nuclear Power Engineering, 2017, 38(4): 128-133. doi: 10.13832/j.jnpe.2017.04.0128 |
[10] | He Kun, Zhao Yuxiang, Dang Ying, Wang Li, Jiang Fan. Fatigue Behavior of TA16 Tube with Surface Defect under High Cycle Loading[J]. Nuclear Power Engineering, 2016, 37(1): 48-51. doi: 10.13832/j.jnpe.2016.01.0048 |
[11] | CHEN Chao, DAN Jianqiang, ZHANG Bo. Sub-Channel Analysis of SCWR Assembly with Double-row Fuel Rods[J]. Nuclear Power Engineering, 2014, 35(2): 27-32. |
[12] | LÜ Pingping, an Shenping. Determination of Elements in Stainless Steel by X-Ray Fluorescence Spectrometry[J]. Nuclear Power Engineering, 2014, 35(3): 167-169. doi: 10.13832/j.jnpe.2014.03.0167 |
[13] | ZENG Xiao-kang, LI Yong-liang, YAN Xiao, XIAO Ze-jun, HUANG Yan-ping. Application of CFD Methods in Research of SCWR Thermo-Hydraulics[J]. Nuclear Power Engineering, 2013, 34(1): 114-120. |
[14] | LIANG Bo, CHEN Le, TANG Rui, ZHANG Qiang. Study on Creep Property of Candidate Stainless Steels for SCWR[J]. Nuclear Power Engineering, 2013, 34(1): 137-139. |
[15] | TAN Xiao-hui, MA Jian-zhong, LIU Yu-jie, DAI Zhen-yu. Experimental Study on Creep/Fatigue Interaction Correlation[J]. Nuclear Power Engineering, 2013, 34(1): 140-145. |
[16] | CHEN Le, TANG Rui, LIANG Bo, ZHANG Qiang, LIU Hong. Study on Low-Cycle Fatigue Property of Candidate Stainless Steels for SCWR[J]. Nuclear Power Engineering, 2013, 34(1): 146-149,156. |
[17] | ZHANG Qiang, QIU Shao-yu, TANG Rui, YIN Kai-ju. Study on Corrosion Behaviors of Stainless Steels and Refractory Alloys in Pseudo-Critical Zone[J]. Nuclear Power Engineering, 2013, 34(1): 157-161. |
[18] | XIONG Ru, QIAO Ying-jie, ZHAO Yu-xiang, TANG Rui, YI Wei, XIAO Ze-jun. Study on High-Cycle Fatigue Behavior of 6XN Stainless Steel and Alloy 825[J]. Nuclear Power Engineering, 2013, 34(5): 76-79,83. |
[19] | PAN Qianfu, LIU Chaohong, TANG Rui, JIANG Mingzhong, YI Wei. Research on 310S for Microalloying with Addition of Titanium and Zirconium[J]. Nuclear Power Engineering, 2012, 33(S2): 70-74. |
[20] | ZHOU Haibin, XIONG Ru, LIU Guiliang, LI Chuanqian, LIU Hong, ZHANG Liang. Fatigue Behavior of Titanium Alloy Ti-4Al-2V under High Cycle Loading at Elevated Temperature[J]. Nuclear Power Engineering, 2012, 33(5): 124-128. |