Yiheng Chen

Dr. Yiheng Chen

orcid

Research Focus & Metrics

Academic Career Length

6Years (2021-Present)

(Calculated once Scilit publication data is synced: current year − year of first publication + 1)

Representative Publications

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16 June 2022 in Journal of Nuclear Materials
Verified
Journal Article
Closed access
ZXZiyang Xie
Ziyang Xie
LGLiping Guo
Liping Guo
YCYiheng Chen
Yiheng Chen
YLYunxiang Long
Yunxiang Long
FLFang Li
Fang Li
YWYuanyun Wen
Yuanyun Wen

8 September 2022 in Journal of Nuclear Materials
Verified
Journal Article
Closed access
YCYiheng Chen
Yiheng Chen
YLYunxiang Long
Yunxiang Long
HLHongtai Luo
Hongtai Luo
ZXZiyang Xie
Ziyang Xie
WLWenbin Lin
Wenbin Lin
YWYuanyun Wen
Yuanyun Wen

28 March 2024 in Materials Science and Engineering: A
Verified
Journal Article
Closed access
LXLiang Xia
Liang Xia
YCYiheng Chen
Yiheng Chen
JHJia Huang
Jia Huang
YWYugang Wang
Yugang Wang
Chenxu WangChenxu Wang
Chenxu Wang
XXXiazi Xiao
Xiazi Xiao

20 April 2024 in Journal of Materials Research and Technology
Verified
Journal Article
Open access
ZYZepeng Yin
Zepeng Yin
LGLiping Guo
Liping Guo
YLYunxiang Long
Yunxiang Long
YCYiheng Chen
Yiheng Chen
ZXZiyang Xie
Ziyang Xie
SJShuoxue Jin
Shuoxue Jin

5 April 2024 in Journal of Nuclear Materials
Verified
Journal Article
Closed access
ZXZiyang Xie
Ziyang Xie
YLYunxiang Long
Yunxiang Long
YCYiheng Chen
Yiheng Chen
HLHongtai Luo
Hongtai Luo
WLWenbin Lin
Wenbin Lin
LGLiping Guo
Liping Guo

25 June 2021 in Metals
Verified
Journal Article
Open access
PDF file
HLHong tai Luo
Hong tai Luo
FLFengfeng Luo
Fengfeng Luo
YCYiheng Chen
Yiheng Chen
JWJiawei Wang
Jiawei Wang
QLQiuxiang Liu
Qiuxiang Liu
LGLiping Guo
Liping Guo
Microstructure and irradiation hardening of V-4Cr-4Ti alloys with different yttrium (Y) contents were studied by self-ion irradiation at 550 °C via TEM and nano-indentation test technology. The peak damage of the V-4Cr-4Ti-xY alloy (x = 0, 0.1, 0.5, and 1, wt.%) irradiated by 2.5 MeV self-ion (V2+) is 8 dpa. Dense dislocation loops were observed in all vanadium alloy samples after irradiation. With the increase of Y content, both average size and number density of dislocation loops using g = near the pole [001] decreased, while the irradiation hardness increment first decreased and then increased. In order to better reduce the irradiation hardening, it is considered that the addition of 0.1 wt.% Y in V-4Cr-4Ti alloy is reasonable.