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科研机构
金属研究所 [26]
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期刊论文 [26]
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2022 [1]
2021 [3]
2019 [2]
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Materials ... [3]
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Temperature-dependent yield strength and deformation mechanism of a casting Ni-based superalloy containing low volume-fraction gamma ' phase
期刊论文
JOURNAL OF ALLOYS AND COMPOUNDS, 2022, 卷号: 905, 页码: 10
作者:
Hou, Kunlei
;
Wang, Min
;
Zhao, Peng
;
Ou, Meiqiong
;
Li, Haoze
收藏
  |  
浏览/下载:20/0
  |  
提交时间:2022/07/01
Ni-based superalloy
Temperature effect
Yield strength anomaly
Deformation mechanism
Orowan looping
Irradiation behaviors of two novel single-phase bcc-structure high-entropy alloys for accident-tolerant fuel cladding
期刊论文
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2021, 卷号: 84, 页码: 230-238
作者:
Zhang, Zijian
;
Han, En-Hou
;
Xiang, Chao
收藏
  |  
浏览/下载:42/0
  |  
提交时间:2021/10/15
High-entropy alloy
Accident-tolerant fuel cladding
Helium-ion irradiation
Microstructure
Irradiation hardening
Formation of Bubble-Loop Complexes During Helium Radiation in Fe-9Cr Steel
期刊论文
FRONTIERS IN ENERGY RESEARCH, 2021, 卷号: 9, 页码: 10
作者:
Shi, Tiantian
;
Liu, Wenbo
;
Su, Zhengxiong
;
Yan, Xu
;
Lu, Chenyang
收藏
  |  
浏览/下载:19/0
  |  
提交时间:2021/12/09
Fe-Cr alloys
bubble-loop complexes
He irradiation
Cr enrichment
dislocation loops
Effects of MeV Fe Ions Irradiation on the Microstructure and Property of Nuclear Grade 304 Stainless Steel: Characterized by Positron Annihilation Spectroscopy, Transmission Electron Microscope and Nanoindentation
期刊论文
ACTA METALLURGICA SINICA-ENGLISH LETTERS, 2021, 页码: 9
作者:
Yan, Honglin
;
Zhang, Zhiming
;
Wang, Jianqiu
;
Okonkwo, Bright O.
;
Han, En-Hou
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  |  
浏览/下载:37/0
  |  
提交时间:2021/10/15
Stainless steel
Irradiation hardening
Positron annihilation
Nanoindentation
Effect of aluminum content on dislocation loops in model FeCrAl alloys
期刊论文
NUCLEAR MATERIALS AND ENERGY, 2019, 卷号: 21, 页码: 7
作者:
Zhou, Xiong
;
Guo, Liping
;
Wei, Yaxia
;
Wang, Hui
;
Chen, Cheng
收藏
  |  
浏览/下载:31/0
  |  
提交时间:2021/02/02
FeCrAl alloy
Dislocation loops
Radiation damage
Accident tolerant fuel cladding
Investigation on low-cycle fatigue behaviors of wrought superalloy GH4742 at room-temperature and 700 degrees C
期刊论文
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2019, 卷号: 751, 页码: 226-236
作者:
Kong, Wei-Wen
;
Yuan, Chao
;
Zhang, Bao-Ning
;
Qin, He-Yong
;
Zhao, Guang-Pu
收藏
  |  
浏览/下载:6/0
  |  
提交时间:2021/02/02
Wrought superalloy GH4742
Low-cycle fatigue
Fatigue life
Cycle hardening and softening
Deformation mechanism
Effects of intragranular defects on helium accumulation damage in nanocrystalline nitrides
期刊论文
JOURNAL OF ALLOYS AND COMPOUNDS, 2018, 卷号: 739, 页码: 401-406
作者:
Lao, YX
;
Niu, WX
;
Shi, YL
;
Du, H
;
Zhang, HB
收藏
  |  
浏览/下载:29/0
  |  
提交时间:2018/06/05
Microstructure Evolution
Radiation Tolerance
Bubble Formation
He Irradiation
Degrees-c
Interfaces
Migration
Ceramics
Study of Irradiation Damage in Domestically Fabricated Nuclear Grade Stainless Steel
期刊论文
ACTA METALLURGICA SINICA, 2017, 卷号: 53, 期号: 12, 页码: 1588-1602
作者:
Deng Ping
;
Peng Qunjia
;
Han En-Hou
;
Ke Wei
;
Sun Chen
收藏
  |  
浏览/下载:23/0
  |  
提交时间:2021/02/02
nuclear grade stainless steel
proton irradiation
dislocation loop
radiation-induced segregation
radiation-induced hardening
Study of Irradiation Damage in Domestically Fabricated Nuclear Grade Stainless Steel
期刊论文
ACTA METALLURGICA SINICA, 2017, 卷号: 53, 期号: 12, 页码: 1588-1602
作者:
Deng Ping
;
Peng Qunjia
;
Han En-Hou
;
Ke Wei
;
Sun Chen
收藏
  |  
浏览/下载:23/0
  |  
提交时间:2021/02/02
nuclear grade stainless steel
proton irradiation
dislocation loop
radiation-induced segregation
radiation-induced hardening
Tensile properties and microstructure of Zr-1.8Nb alloy subjected to 140-MeV C4+ ion irradiation
期刊论文
ELSEVIER SCIENCE BV, 2017, 卷号: 495, 页码: 138-145
作者:
Yang, H. L.
;
Kano, S.
;
Matsukawa, Y.
;
Shen, J. J.
;
Zhao, Z. S.
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  |  
浏览/下载:226/0
  |  
提交时间:2018/01/10
Zr-nb Alloy
High Energy Ion irradiatIon
Dislocation Loops
Mechanical Properties
Strengthening
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