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科研机构
金属研究所 [8]
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期刊论文 [8]
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2022 [1]
2021 [1]
2019 [3]
2017 [2]
2011 [1]
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Deformation and cracking behaviors of proton-irradiated 308L stainless steel weld metal strained in simulated PWR primary water
期刊论文
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2022, 卷号: 120, 页码: 36-52
作者:
Lin, Xiaodong
;
Peng, Qunjia
;
Han, En-Hou
;
Ke, Wei
收藏
  |  
浏览/下载:19/0
  |  
提交时间:2022/07/01
Stainless steel weld metal
Proton irradiation
Deformation microstructures
Irradiation assisted stress corrosion cracking
Grain and phase boundaries
Proton irradiation assisted localized corrosion and stress corrosion cracking in 304 nuclear grade stainless steel in simulated primary PWR water
期刊论文
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2021, 卷号: 65, 页码: 61-71
作者:
Deng, Ping
;
Peng, Qunjia
;
Han, En-Hou
;
Ke, Wei
;
Sun, Chen
收藏
  |  
浏览/下载:6/0
  |  
提交时间:2021/03/15
Stainless steel
AFM
TEM
High temperature corrosion
Stress corrosion
Study on Irradiation Assisted Stress Corrosion Cracking of Nuclear Grade 304 Stainless Steel
期刊论文
ACTA METALLURGICA SINICA, 2019, 卷号: 55, 期号: 3, 页码: 349-361
作者:
Deng Ping
;
Sun Chen
;
Peng Qunjia
;
Han En-Hou
;
Ke Wei
收藏
  |  
浏览/下载:5/0
  |  
提交时间:2021/02/02
nuclear grade stainless steel
proton irradiation
localized deformation
corrosion
irradiation assisted stress corrosion cracking
Study on Irradiation Assisted Stress Corrosion Cracking of Nuclear Grade 304 Stainless Steel
期刊论文
ACTA METALLURGICA SINICA, 2019, 卷号: 55, 期号: 3, 页码: 349-361
作者:
Deng Ping
;
Sun Chen
;
Peng Qunjia
;
Han En-Hou
;
Ke Wei
收藏
  |  
浏览/下载:6/0
  |  
提交时间:2021/02/02
nuclear grade stainless steel
proton irradiation
localized deformation
corrosion
irradiation assisted stress corrosion cracking
Study on Irradiation Assisted Stress Corrosion Cracking of Nuclear Grade 304 Stainless Steel
期刊论文
ACTA METALLURGICA SINICA, 2019, 卷号: 55, 期号: 3, 页码: 349-361
作者:
Deng Ping
;
Sun Chen
;
Peng Qunjia
;
Han En-Hou
;
Ke Wei
收藏
  |  
浏览/下载:2/0
  |  
提交时间:2021/02/02
nuclear grade stainless steel
proton irradiation
localized deformation
corrosion
irradiation assisted stress corrosion cracking
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
RESEARCH TRENDS ON MICRO AND NANO-SCALE MATERIALS DEGRADATION IN NUCLEAR POWER PLANT
期刊论文
ACTA METALLURGICA SINICA, 2011, 卷号: 47, 期号: 7, 页码: 769-776
作者:
Han En-Hou
收藏
  |  
浏览/下载:14/0
  |  
提交时间:2021/02/02
key material in nuclear power plant
stainless steel
nickel-based alloy
low alloy steel
zirconium alloy
corrosion
stress corrosion cracking
corrosion fatigue
flow assisted corrosion
irradiation degradation
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