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Research progress on preparation technology of oxide dispersion strengthened steel for nuclear energy
期刊论文
International Journal of Extreme Manufacturing, 2021, 卷号: 3, 期号: 3
作者:
Wang,Jianqiang
;
Liu,Sheng
;
Xu,Bin
;
Zhang,Jianyang
;
Sun,Mingyue
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浏览/下载:45/0
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提交时间:2021/10/15
nuclear energy
oxide dispersion strengthened steel
preparation process
powder metallurgy
additive forging
Supramolecular PFPE gel lubricant with anti-creep capability under irradiation conditions at high vacuum
期刊论文
Chemical Engineering Journal, 2020, 期号: 409, 页码: 1-13
作者:
Yanyan Bai 1,2
;
Chaoyang Zhang 1
;
Qiangliang Yu 1
;
Jiaying Zhang 1
;
Ming Zhang 1
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浏览/下载:45/0
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提交时间:2021/12/13
Recent progresses on designing and manufacturing of bulk refractory alloys with high performances based on controlling interfaces
期刊论文
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2020, 卷号: 52
作者:
Zhang, T.
;
Deng, H. W.
;
Xie, Z. M.
;
Liu, R.
;
Yang, J. F.
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浏览/下载:52/0
  |  
提交时间:2020/10/26
Interface controlling
Designing and manufacturing
Refractory alloys
Structure and performance
Effect of interstitial < 100 > dislocation loop on expansion of micro-crack in body centered cubic iron investigated by molecular dynamics method
期刊论文
ACTA PHYSICA SINICA, 2020, 卷号: 69, 期号: 11, 页码: 8
作者:
Liang Jin-Jie
;
Gao Ning
;
Li Yu-Hong
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浏览/下载:18/0
  |  
提交时间:2022/01/12
radiation damage
micro-crack
dislocation loop
molecular dynamics simulation
In-beam creep of SiCf/SiC minicomposites under uniaxial tensile loading
期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 533, 页码: 7
作者:
Chen, Jiachao
;
Jacques, Sylvain
;
Barthe, Marie-France
;
Zhang, Chonghong
;
Desgardin, Pierre
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  |  
浏览/下载:14/0
  |  
提交时间:2022/01/18
SiCf/SiC composite
High-temperature mechanical testing
Irradiation creep
Clamping system
Nanoindentation Study on the Creep Characteristics and Hardness of Ion-Irradiated Alloys
期刊论文
MATERIALS, 2020, 卷号: 13, 期号: 14, 页码: -
作者:
Zhu, ZB
;
Huang, HF
;
Liu, JZ
;
Ye, LF
;
Zhu, ZY
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浏览/下载:78/0
  |  
提交时间:2021/09/06
STRAIN-RATE SENSITIVITY
MICROSTRUCTURAL EVOLUTION
FERRITIC STEELS
GH3535 ALLOY
TEMPERATURE
INDENTATION
REACTOR
800H
DEFORMATION
DUCTILITY
Ion-beam-assisted characterization of quinoline-insoluble particles in nuclear graphite
期刊论文
NUCLEAR SCIENCE AND TECHNIQUES, 2020, 卷号: 31, 期号: 10, 页码: -
作者:
Huang, Q
;
Han, XQ
;
Liu, P
;
Li, JJ
;
Lei, GH
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浏览/下载:3/0
  |  
提交时间:2021/09/06
TRANSMISSION ELECTRON-MICROSCOPY
NEUTRON-IRRADIATION
RAMAN-SPECTRA
DAMAGE
ENERGY
IG-110
CREEP
Excellent irradiation tolerance and mechanical behaviors in high-entropy metallic glasses
期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2019, 卷号: 527, 页码: 8
作者:
Wang Y(王洋)
;
Zhang K(张坤)
;
Feng YH(冯义辉)
;
Li YS(李炎森)
;
Tang WQ(唐伟奇)
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  |  
浏览/下载:143/0
  |  
提交时间:2020/03/11
High-entropy metallic glass
Irradiation damage
Serrated flow
Creep behavior
Quantitative investigation on sink strength of nano-grain boundary for irradiation resistance
期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2019, 卷号: 526, 页码: 12
作者:
Mao, Pengyan
;
Cui, Jingping
;
Chen, Yangchun
;
Qiu, Jianhang
;
Jin, Qun
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  |  
浏览/下载:26/0
  |  
提交时间:2022/01/19
Nano-grain boundary
Irradiation tolerance
Grain boundary characters
Grain size
Sink strength
Evaluation of displacement cross-section for neutron-irradiated 15-15Ti steel and its swelling behavior in CiADS radiation environment
期刊论文
ANNALS OF NUCLEAR ENERGY, 2019, 卷号: 133, 页码: 937-949
作者:
Korepanova, N.
;
Gu, Long
;
Zhang, Lu
;
Dai, Yong
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浏览/下载:57/0
  |  
提交时间:2019/11/10
15-15Ti steel
Displacement cross-section
CIADS
Swelling
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