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Chinese Academy of Sciences Institutional Repositories Grid
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CAS IR Grid
机构
金属研究所 [21]
上海硅酸盐研究所 [1]
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OAI收割 [22]
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期刊论文 [22]
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2022 [1]
2019 [3]
2018 [3]
2017 [1]
2016 [1]
2014 [2]
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学科主题
Materials ... [4]
Metallurgy... [2]
Nuclear Sc... [2]
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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
OAI收割
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:98/0
  |  
提交时间:2022/07/01
Stainless steel weld metal
Proton irradiation
Deformation microstructures
Irradiation assisted stress corrosion cracking
Grain and phase boundaries
Study on Irradiation Assisted Stress Corrosion Cracking of Nuclear Grade 304 Stainless Steel
期刊论文
OAI收割
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:17/0
  |  
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
OAI收割
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:17/0
  |  
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
OAI收割
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:25/0
  |  
提交时间:2021/02/02
nuclear grade stainless steel
proton irradiation
localized deformation
corrosion
irradiation assisted stress corrosion cracking
Evaluation of stress corrosion cracking susceptibility of forged 316 stainless steel in simulated primary water
期刊论文
OAI收割
MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION, 2018, 卷号: 69, 期号: 3, 页码: 328-336
作者:
Zhu, RL
;
Wang, JQ
;
Ming, HL
;
Zhang, ZM
;
Han, EH
  |  
收藏
  |  
浏览/下载:29/0
  |  
提交时间:2018/06/05
High-temperature Water
Environmentally Assisted Cracking
Reactor Primary Water
Pwr Primary Water
Pressurized-water
Dissolved-oxygen
Oxidation Behavior
Nickel-alloys
Growth
Metal
Correlation of microstructure and stress corrosion cracking initiation behaviour of the fusion boundary region in a SA508 Cl. 3-Alloy 52M dissimilar weld joint in primary pressurized water reactor environment
期刊论文
OAI收割
CORROSION SCIENCE, 2018, 卷号: 132, 页码: 9-20
作者:
Dong, LJ
;
Peng, QJ
;
Xue, H
;
Han, EH
;
Ke, W
  |  
收藏
  |  
浏览/下载:72/0
  |  
提交时间:2018/06/05
Low-alloy Steel
High-temperature Water
Heat-affected Zone
Bwr Coolant Environments
Grain-boundary
Metal Weld
Assisted Cracking
Stainless-steel
Chromium Depletion
Residual-stress
Structural, mechanical and corrosion studies of Cr-rich inclusions in 152 cladding of dissimilar metal weld joint
期刊论文
OAI收割
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 498, 页码: 9-19
作者:
Li, YF
;
Wang, JQ
;
Han, EH
;
Yang, CD
;
Wang, JQ (reprint author), Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Liaoning, Peoples R China.
  |  
收藏
  |  
浏览/下载:55/0
  |  
提交时间:2018/06/05
Pressurized-water Reactors
Environmentally-assisted Cracking
Safe-end
Quantitative Assessment
Secondary-side
Residual-stresses
High-temperature
Fusion Boundary
Base Alloys
Part 1
Strain-rate dependent fatigue behavior of 316LN stainless steel in high-temperature water
期刊论文
OAI收割
JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 489, 页码: 33-41
Tan, Jibo
;
Wu, Xinqiang
;
Han, En-Hou
;
Ke, Wei
;
Wang, Xiang
;
Sun, Haitao
收藏
  |  
浏览/下载:36/0
  |  
提交时间:2017/08/17
316LN stainless steel
Corrosion fatigue
Strain rate
High-temperature water
Environmentally assisted cracking
Mesoporogen-Free Synthesis of Hierarchically Structured Zeolites with Variable Si/Al Ratios via a Steam-Assisted Crystallization Process
期刊论文
OAI收割
ACS APPLIED MATERIALS & INTERFACES, 2016, 卷号: 8, 期号: 11, 页码: 7118-7124
作者:
He, Xiaoyun
;
Ge, Tongguang
;
Hua, Zile
;
Zhou, Jian
;
Lv, Jian
收藏
  |  
浏览/下载:32/0
  |  
提交时间:2017/02/27
hierarchically structured zeolites
mesoporogen-free
steam-assisted crystallization
Si/Al ratios
cracking
Effect of dissolved oxygen content on stress corrosion cracking of a cold worked 316L stainless steel in simulated pressurized water reactor primary water environment
期刊论文
OAI收割
Journal of Nuclear Materials, 2014, 卷号: 446, 期号: 1-3, 页码: 15-26
L. T. Zhang
;
J. Q. Wang
收藏
  |  
浏览/下载:35/0
  |  
提交时间:2014/04/18
high-temperature water
assisted cracking
alloy 690tt
pure water
growth
behavior
dependence
chemistry
coolant
model