[1] | Wang Qi, Chen Guoshuai, Zhou Zhangjian, Xiong Ru, Zheng Jiyun, Tang Rui, Zhang Lefu. Effect of N and Al Addition on Microstructure and Mechanical Properties of Modified 25Ni-20Cr Austenitic Stainless Steel Aged at 700℃[J]. Nuclear Power Engineering, 2023, 44(5): 275-283. doi: 10.13832/j.jnpe.2023.05.0275 |
[2] | Zhong Lei, Chen Deqi, Yu Hongxing, Liu Hanzhou, Chen Mingjing, Deng Jian, Ding Shuhua, Wu Dan. Experimental Study on Microstructure and Wetting Properties of N36 Zirconium Alloy Oxide Layer[J]. Nuclear Power Engineering, 2023, 44(1): 37-44. doi: 10.13832/j.jnpe.2023.01.0037 |
[3] | Jia Yuzhen, Qiu Jun, Cheng Zhuqing, Yang Zhongbo. Effect of Final Annealing Temperature on Microstructure and Properties of N36 Alloy Tube[J]. Nuclear Power Engineering, 2023, 44(S1): 163-167. doi: 10.13832/j.jnpe.2023.S1.0163 |
[4] | Huang Tao, Su Haozhan, Zhang Lefu, Chen kai. Effect of Microstructure on Corrosion Behavior of Alloy 800H in Supercritical Water[J]. Nuclear Power Engineering, 2023, 44(5): 251-258. doi: 10.13832/j.jnpe.2023.05.0251 |
[5] | Wang Jieyi, Li Qiang, Lian Aojie, Liang Xue, Peng Jianchao, Yao Meiyi. Microstructure and Corrosion Behavior of Zr-0.2Cu-xNb Alloys[J]. Nuclear Power Engineering, 2020, 41(1): 43-48. doi: 10.13832/j.jnpe.2020.01.0043 |
[6] | Zhuang Yaping, Ma Baisong. Design Improvement of Reactor Vessel Shielding Component[J]. Nuclear Power Engineering, 2020, 41(5): 185-188. |
[7] | Li Rui. Study on Microstructure and Corrosion Mechanism for Two Kinds of Zirconium Alloy[J]. Nuclear Power Engineering, 2018, 39(5): 43-46. doi: 10.13832/j.jnpe.2018.05.0043 |
[8] | 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 |
[9] | Li Shunping, Peng Qian, Yang Zhongbo, Chen Le, Li Weijun. Study on Microstructure and Mechanical Properties of Zr-Sn-Nb Alloys Thin Sheet Weld[J]. Nuclear Power Engineering, 2017, 38(4): 149-152. doi: 10.13832/j.jnpe.2017.04.0149 |
[10] | Lan Guangyou, Tang Bin, Pu Yongxing, HE Zujuan, Liu Siwei, Yuan Zhengchuan, Hu Rui. Microstructure Evolution in Hydrogenation and Dehydrogenation Process of Zircaloy[J]. Nuclear Power Engineering, 2017, 38(2): 88-92. doi: 10.13832/j.jnpe.2017.02.0088 |
[11] | Guo Lina, Han Hua, Bian Wei, Chu Fengmin, Qian Jin, Liang Zhengqiang. Study on Microstructure of Zr-2.5Nb Pressure Tube Material[J]. Nuclear Power Engineering, 2017, 38(S1): 89-93. doi: 10.13832/j.jnpe.2017.S1.0089 |
[12] | Nie Shuhong, Liang Zhengqiang. Microstructure of Heat-Affected Zone in a Weld Joint between Alloy 690 and Alloy 152[J]. Nuclear Power Engineering, 2017, 38(4): 139-144. doi: 10.13832/j.jnpe.2017.04.0139 |
[13] | Xi Hang, ZHang Haisheng, Wu Lu, SuN Kai, Peng Yanhua, MO Huajun. Fracture Mechanism of Neutron Irradiated B4C/Al Composite Material[J]. Nuclear Power Engineering, 2017, 38(S1): 129-132. doi: 10.13832/j.jnpe.2017.S1.0129 |
[14] | Li Chengliang, Li Yuanfei, MO Huajun, Liu Feihua, Chen Jun, SHu Guogang. Irradiation Damage Effects on Microstructure of Reactor Pressure Vessel Steels[J]. Nuclear Power Engineering, 2017, 38(S1): 54-57. doi: 10.13832/j.jnpe.2017.S1.0054 |
[15] | Sun Yongduo, Xiong Ru, Qiu Shaoyu, Song Yiyang, Wang Jiamei, Zhang Lefu. Study on Stress Corrosion Cracking of Welded Joint with Inconel 690 and 321 Stainless Steel[J]. Nuclear Power Engineering, 2017, 38(4): 153-158. doi: 10.13832/j.jnpe.2017.04.0153 |
[16] | Long Chongsheng, Wei Tianguo, Chen Hongsheng, Xiao Hongxing, Zhao Yi. Quantitative Characterization of Micro-defect in Zircaloy Oxide Films[J]. Nuclear Power Engineering, 2016, 37(2): 87-90. doi: 10.13832/j.jnpe.2016.02.0087 |
[17] | Xu Jiangming, Xu Chunrong, Fan Baoquan, Wang Shizhong. Microstructure and Tensile Properties of 304L Austenitic Stainless Joints Produced by Friction Stir Welding and Tungsten Inert-Gas Welding[J]. Nuclear Power Engineering, 2016, 37(1): 57-61. doi: 10.13832/j.jnpe.2015.06.0057 |
[18] | LI Yuan-yuan, DAI Sheng-ping, YANG Jing, PEI Qi-lin, QIAO Hui-wu. Study on Preparation of B4C-Zircaloy Annular Burnable Absorber[J]. Nuclear Power Engineering, 2013, 34(3): 28-31. |
[19] | DAI Xun, LIU Hong, WANG Pengfei, WANG Ying, ZHAO Wenjin. Study on Microstructure and Texture of Processed N18 Plates by EBSD[J]. Nuclear Power Engineering, 2012, 33(S2): 17-21. |
[20] | DAI Xun, LIU Hong, WANG Pengfei, WANG Ying, ZHAO Wenjin, SHI Minghua. Study on Microstructure of Hot Extruded N36 Zirconium Alloy Tubes[J]. Nuclear Power Engineering, 2012, 33(S2): 43-46,78. |