[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] | Su Haozhan, Huang Tao, Zhang Lefu, Chen Kai. Effect of Water Chemistry on the Performance of Alloy 800H in Supercritical Water-cooled Reactor[J]. Nuclear Power Engineering, 2023, 44(5): 267-274. doi: 10.13832/j.jnpe.2023.05.0267 |
[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] | 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 |
[5] | Guo Yanhui, Deng Dong, Sun Zaozhan, Huang Bingchen. Microstructure and Mechanical Properties of Heat-affected Zone of Repeated Welding on 304 Stainless Steel[J]. Nuclear Power Engineering, 2021, 42(4): 198-202. doi: 10.13832/j.jnpe.2021.04.0198 |
[6] | Zhang Hongliang, Zhu Mingdong, Sun Xiaoyang, He Daming, Wang Qingtian, Su Dongchuan, Li Ning, Zeng Chang, He Xikou. Research on Fundamental Characteristics of Nuclear Grade 316H Stainless Steel at Ultra High Temperature[J]. Nuclear Power Engineering, 2021, 42(4): 270-276. doi: 10.13832/j.jnpe.2021.04.0270 |
[7] | Liu Zhenshun, Sun Jinxiong, Zhang Lei, Zhen Hongdong. Numerical Comparison Study on Residual Life Specification Prediction Methods of Austenitic Stainless Steel Nuclear Piping with Planar Defects Based on ASME and RSE-M Regulations[J]. Nuclear Power Engineering, 2018, 39(5): 85-90. doi: 10.13832/j.jnpe.2018.05.0085 |
[8] | Wu Shi, He Xinfu, JiA Lixia, Dou Yankun, Wang Dongjie, Yang Wen. Modeling of Evolution of Radiation-induced Frank Loops in Austenitic Stainless Steels[J]. Nuclear Power Engineering, 2017, 38(S1): 99-104. doi: 10.13832/j.jnpe.2017.S1.0099 |
[9] | Chen Le, HE Kun, Liang Bo, Wang Li. Study on Low-Cycle Fatigue Property of 316 Stainless Steel at Room Temperature and 350℃[J]. Nuclear Power Engineering, 2017, 38(3): 51-55. doi: 10.13832/j.jnpe.2017.03.0051 |
[10] | 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. |
[11] | Luo Qiang, CheN Yong, Qiu Shaoyu, Zhou Jun, He Kun. Study on Low Temperature Thermal Aging Behavior of 316LN Austenitic Stainless Steel Weld[J]. Nuclear Power Engineering, 2014, 35(4): 102-105. doi: 10.13832/j.jnpe.2014.04.0102 |
[12] | LUO Feng, ZHOU Tao, CHENG Wan-xu, SU Zi-wei, CHEN Juan. Sensitivity Analysis for Transient of Partial Loss of Reactor Coolant Flow of Super LWR[J]. Nuclear Power Engineering, 2013, 34(4): 100-105. |
[13] | XIA Bangyang, YANG Ping, WANG Lianjie, LI Qing, LI Xiang. Study on Reactivity Control Method for Supercritical Water-Cooled Reactor CSR1000[J]. Nuclear Power Engineering, 2013, 34(1): 26-30. |
[14] | XIAO Ze-jun, LI Xiang, HUANG Yan-ping, TANG Rui, LUO Qi, ZANG Feng-gang, LI Qing, LI Peng-zhou, YI Wei. Overview of Research and Development (Phase Ⅰ) on Key Technologies for Supercritical Water-Cooled Reactor[J]. Nuclear Power Engineering, 2013, 34(1): 1-4,14. |
[15] | 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. |
[16] | 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. |
[17] | XIONG Ru, ZHAO Yu-xiang, QIAO Ying-jie, ZHANG Qiang, WANG Hao, TANG Rui. Study on High-Cycle Fatigue Behavior of Candidate Stainless Steels for SCWR[J]. Nuclear Power Engineering, 2013, 34(1): 150-156. |
[18] | 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. |
[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] | YIN Kaiju, QIU Shaoyu, TANG Rui, ZHANG Qiang, ZHANG Lefu. Investigation of Oxide Scale on 304NG Exposed in Supercritical Water[J]. Nuclear Power Engineering, 2012, 33(1): 88-92. |