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TEM studies of 1 MeV Fe+ ion-irradiated W alloys by wet chemical method: high-temperature annealing and deuterium retention
被引:5
作者:
Ding, Xiao-Yu
[1
,2
]
Liu, Jia-Qin
[3
,4
]
Luo, Lai-Ma
[3
,4
,5
]
Xu, Qiu
[6
]
Gao, Xiang
[7
]
Huang, Jian-Jun
[1
]
Yu, Bin
[2
]
Li, Jian-Gang
[1
,7
]
Wu, Yu-Cheng
[3
,4
,5
]
机构:
[1] Shenzhen Univ, Adv Energy Res Ctr, Shenzhen 518060, Peoples R China
[2] Shenzhen Univ, Coll Optoelect Engn, Key Lab Optoelect Devices & Syst, Minist Educ & Guangdong Prov, Shenzhen 518060, Peoples R China
[3] Key Lab Adv Funct Mat & Devices Anhui Prov, Hefei 230009, Anhui, Peoples R China
[4] Base Introducing Talents Discipline Univ Adv Clea, Hefei 230009, Anhui, Peoples R China
[5] Hefei Univ Technol, Sch Mat Sci & Engn, Hefei 230009, Anhui, Peoples R China
[6] Kyoto Univ, Inst Integrated Radiat & Nucl Sci, Osaka Fu 5900494, Japan
[7] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China
基金:
中国国家自然科学基金;
关键词:
tungsten;
ion irradiation;
microstructure evolution;
annealing effect;
TEM;
deuterium retention;
IN-SITU;
TUNGSTEN;
MICROSTRUCTURE;
DAMAGE;
NEUTRON;
NANOCRYSTALLINE;
COMPOSITES;
BEHAVIOR;
LOOP;
D O I:
10.1088/1741-4326/aaeaee
中图分类号:
O35 [流体力学];
O53 [等离子体物理学];
学科分类号:
070204 ;
080103 ;
080704 ;
摘要:
In this study, the microstructural changes in irradiated W-1 wt%Pr2O3, W-1 wt%La2O3, W-1 wt%TiC and W-1 wt%ZrC specimens by 1 MeV Fe+ ion irradiation to doses of 1 dpa at room temperature have been characterized by transmission electron microscopy (TEM) to understand the radiation damage. The specimens of 1 dpa were consecutively annealed at temperatures of 600 degrees C, 800 degrees C, 900 degrees C and 1100 degrees C for 1h, and the post-irradiation annealing effect on the microstructure was studied. Microstructural features such as dislocations, dislocation loops and dense dislocation networks were observed by the means of TEM. There was a significant change in the microstructure of the tungsten (W) after irradiation and post-irradiation annealing. W-1 wt%TiC likely consisted of fewer radiation-induced defects and hence exhibits higher resistance to radiation-induced microstructural changes than the others. The general trend is that the density of defect clusters decreases while the average size of the clusters increases with the annealing temperature. A complete removal of dislocation structures at 1100 degrees C occurred in all materials. The irradiation damage effect of Fe+ ions on the deuterium retention of as-synthesized W-based composites was investigated. Thermal desorption spectroscopy of W implanted with D-2 (-) ions was performed using the low-energy ion irradiation system of Kyoto University. Compared with the samples without Fe preirradiation, the deuterium retention of the four composites increased after Fe+ pre-irradiation. The retained amount of deuterium was also increased with the increase in the Fe+ irradiation dose. This is of vital importance to the scientific community working on these materials for extreme irradiating environments.
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页数:12
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