Study on irradiation hardening by He+ and subsequent V/self-ion irradiation in V-4Cr-4Ti under near-service conditions

被引：1
作者：
Zhang, Shoushuai [1 ,2 ]
Jiang, Shaoning [1 ,2 ]
Lin, Jianghai [1 ,2 ]
Xia, Yuhai [1 ,2 ]
Guo, Liping [3 ]
Zheng, Pengfei [4 ]
机构：
[1] Qilu Univ Technol, Shandong Acad Sci, Sch Mech Engn, Jinan 250353, Peoples R China
[2] Shandong Inst Mech Design & Res, Jinan 250031, Peoples R China
[3] Wuhan Univ, Sch Phys & Technol, Accelerator Lab, Wuhan 430072, Peoples R China
[4] Southwestern Inst Phys, Chengdu 610041, Peoples R China
来源：
NUCLEAR MATERIALS AND ENERGY | 2024年 / 38卷
基金：
中国国家自然科学基金;
关键词：
V-4Cr-4Ti; V/self-ion; Dislocation loops; Irradiation hardening; EVOLUTION; BUBBLES; PRECIPITATION; STRENGTH; ALLOYS; GAS;
D O I：
10.1016/j.nme.2024.101624
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
V-4Cr-4Ti was irradiated by He+ and subsequent V/self-ions at 773 K to simulate the effect of the damages generated under near-service conditions on irradiation hardening. Microstructure observation and hardness test were carried out by transmission electron microscopy (TEM) and nanoindentation testing. Microstructure analysis showed that bubbles, dislocation loops and precipitates were produced whether samples were irradiated by He+ or He+/V+. Edge dislocation was observed by high -resolution images. The nanoindentation results showed that hardening appeared after irradiation, and hardness increment after He+ irradiation is 4.41 GPa, 6.2 GPa for He+/V+. Meanwhile, based on damage characterization, the irradiation hardening was also analyzed using the dispersion barrier hardening model (DBH), which showed that the main cause of hardening was dislocation loops. In addition, the deviation was discussed between the hardness increment obtained by nanoindentation testing and that calculated based on DBH.
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页数：9
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