Effect of hydrogen ion irradiation on the mechanical properties of thermally aged Z3CN20.09M duplex stainless steel

被引：0
作者：
Lei, Penghui [1 ]
Jiang, Ni [2 ]
Hao, Jiannan [3 ]
Peng, Qing [3 ,4 ]
Qi, Pan [5 ]
Shi, Fangjie [6 ]
Hang, Yuhua [6 ]
Li, Qianwu [6 ]
Ye, Chao [2 ]
机构：
[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Peoples R China
[2] Northwestern Polytech Univ, Inst Clean Energy, Yangtze River Delta Res Inst, Taicang 215400, Peoples R China
[3] Northwestern Polytech Univ, Sch Mat Sci & Engn, Xian 710072, Peoples R China
[4] Chinese Acad Sci, Inst Mech, State Key Lab Nonlinear Mech, Beijing 100190, Peoples R China
[5] China Nucl Power Operat Technol Corp LTD, Wuhan 430223, Peoples R China
[6] Suzhou Nucl Power Res Inst, Suzhou 215004, Peoples R China
来源：
VACUUM | 2025年 / 231卷
基金：
中国国家自然科学基金;
关键词：
Z3CN20.09M duplex alloy; Hydrogen ions irradiation; Nanohardness; TEM in-situ tensile test; EMBRITTLEMENT; FERRITE; FE; CR; EVOLUTION; ALLOY;
D O I：
10.1016/j.vacuum.2024.113757
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
In order to investigate the synergistic effect of thermal aging and hydrogen, Z3CN20.09M duplex stainless steels (DSS) were thermal aged at 400 C-degrees and then the irradiated by hydrogen ions. Due to the segregation of the Fe and Cr elements induced by spinodal decomposition, the nanohardness of the ferrite phase increased after thermal aging process. The irradiation effects by hydrogen ion could further increase the nanohardness of the damage region. But the {011}<111> slip system structures formed by the irradiation significantly suppressed the hardening effects of the ions irradiation induced dislocations and spinodal decomposition induced element segregation. During the in-situ transmission electron microscopy (TEM) tensile process, severe deformation occurred and extended along a slip band that ran diagonally across the entire sample region. At last, a cracking formed at the deformation center area and propagated along the crack tip towards the irradiation damage side, ultimately leading to the sample fracture. This study serves as a valuable reference for improving the properties of Z3CN20.09M DSS utilized in nuclear plants.
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页数：7
相关论文
共 44 条
[1]  
Ali I., 2024, Radiat. Phys. Chem., V224
[2]   In situ electrochemical nanoindentation: A technique for local examination of hydrogen embrittlement [J].
Barnoush, Afrooz ;
Vehoff, Horst .
CORROSION SCIENCE, 2008, 50 (01) :259-267
[3]   Recent developments in the study of hydrogen embrittlement: Hydrogen effect on dislocation nucleation [J].
Barnoush, Afrooz ;
Vehoff, Horst .
ACTA MATERIALIA, 2010, 58 (16) :5274-5285
[4]   HYDROGEN-ENHANCED LOCALIZED PLASTICITY - A MECHANISM FOR HYDROGEN-RELATED FRACTURE [J].
BIRNBAUM, HK ;
SOFRONIS, P .
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 1994, 176 (1-2) :191-202
[5]   Degradation of impact toughness in cast stainless steels during long-term thermal aging [J].
Byun, Thak Sang ;
Collins, David A. ;
Lach, Timothy G. ;
Carter, Emily L. .
JOURNAL OF NUCLEAR MATERIALS, 2020, 542
[6]   In-situ TEM study on the evolution of dislocation loops and bubbles in CeO2 during Kr+ single-beam and Kr+-H2+ dual-beam synergetic irradiation [J].
Cao, Ziqi ;
Ran, Guang ;
Wang, Zhen ;
Li, Yipeng ;
Wu, Xiaoyong ;
Wu, Lu ;
Huang, Xiuyin ;
Mo, Huajun .
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2022, 123 :49-59
[7]  
Chang Q., 2024, J. Nucl. Mater.
[8]   Effects of thermal aging and low-fluence neutron irradiation on the mechanical property and microstructure of ferrite in cast austenitic stainless steels [J].
Chen, Siwei ;
Miyahara, Yuichi ;
Nomoto, Akiyoshi ;
Nishida, Kenji .
ACTA MATERIALIA, 2019, 179 :61-69
[9]   Microstructure and corrosion resistance of Z3CN20.09M stainless steels after different thermo-mechanical processing [J].
Chen, Xufeng ;
Tian, Donghua ;
Ling, Ligong ;
Liu, Tingguang ;
Wang, Hui ;
Chen, Yinqiang ;
Lu, Yonghao .
JOURNAL OF NUCLEAR MATERIALS, 2023, 577
[10]   Investigation on hydrogen embrittlement and failure characteristics of Zr-4 cladding based on the GTN method [J].
Deng, Yangbin ;
Liao, Haoyu ;
He, Yanan ;
Yin, Yuan ;
Pellegrini, Marco ;
Su, Guanghui ;
Okamoto, Koji ;
Wu, Yingwei .
NUCLEAR MATERIALS AND ENERGY, 2023, 36
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