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期刊论文 [10]
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Influence of chromium of low content on the corrosion behavior of SA106B carbon steels in high-temperature pressurized LiOH medium
期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2023, 卷号: 414, 页码: 10
作者:
Zheng, Kexin
;
Hu, Hongxiang
;
Wang, Zhengbin
;
Zheng, Yugui
;
Shang, Xianhe
;
Zhang, Wei
;
Zhao, Liang
收藏
  |  
浏览/下载:2/0
  |  
提交时间:2025/04/27
Electrochemical measurements
Nuclear power plant
Carbon Steel
Lithium hydroxide corrosion
High-temperature corrosion
Oxidation
Experimental study of stratification behavior of the steady two-liquid corium pool
期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2022, 卷号: 391, 页码: 8
作者:
Xue, Baoquan
;
Yang, Yaqian
;
Liang, Tian
;
Chen, Bo
;
Ma, Yingche
;
Liu, Kui
;
Shan, Hongyi
;
Kang, Taifeng
;
Gu, Peiwen
收藏
  |  
浏览/下载:205/0
  |  
提交时间:2022/07/01
Severe accident
In-vessel melt retention
Stratification behavior
Sub-oxidized corium
Layer inversion
Effect of dissolved hydrogen on corrosion of 316NG stainless steel in high temperature water
期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2015, 卷号: 295, 页码: 403-414
作者:
Dong, Lijin
;
Peng, Qunjia
;
Zhang, Zhiming
;
Shoji, Tetsuo
;
Han, En-Hou
;
Ke, Wei
;
Wang, Lei
;
qunjiapeng@imr.ac.cn
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浏览/下载:150/0
  |  
提交时间:2016/04/21
Cavitation erosion and jet impingement erosion mechanism of cold sprayed Ni-Al2O3 coating
期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2011, 卷号: 241, 期号: 12, 页码: 4929-4937
作者:
Hu, H. X.
;
Jiang, S. L.
;
Tao, Y. S.
;
Xiong, T. Y.
;
Zheng, Y. G.
收藏
  |  
浏览/下载:117/0
  |  
提交时间:2021/02/02
Predicting the preferential sites to liquid droplet erosion of the bellows assemblies by CFD
期刊论文
Nuclear Engineering and Design, 2011, 卷号: 241, 期号: 6, 页码: 2295-2306
作者:
H. X. Hu
;
Y. G. Zheng
;
C. B. Liu
Adobe PDF(3651Kb)
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收藏
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浏览/下载:116/0
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提交时间:2012/04/13
Nuclear-power-plant
U-shaped Bellows
Wear Sites
Feedwater Heater
Failure Analysis
Disturbed Flow
Ductile Metals
Corrosion
Impact
Hydrodynamics
Trans-twins stress corrosion cracking behaviors of Alloy 690TT in lead-containing caustic solution at 330 degrees C
期刊论文
Nuclear Engineering and Design, Nuclear Engineering and Design, 2011, 2011, 卷号: 241, 241, 期号: 12, 页码: 4944-4952, 4944-4952
作者:
Z. M. Zhang
;
J. Q. Wang
;
E. H. Han
;
W. Ke
Adobe PDF(1083Kb)
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浏览/下载:81/0
  |  
提交时间:2012/04/13
High-temperature Water
High-temperature Water
Grain-boundary Misorientation
Grain-boundary Misorientation
Ni-base Alloys
Ni-base Alloys
Chromium Depletion
Chromium Depletion
Quantitative Assessment
Quantitative Assessment
Secondary-side
Secondary-side
Heat-treatment
Heat-treatment
Resistance
Resistance
Oxide
Oxide
Microstructure
Microstructure
Cavitation erosion and jet impingement erosion mechanism of cold sprayed Ni-Al(2)O(3) coating
期刊论文
Nuclear Engineering and Design, 2011, 卷号: 241, 期号: 12, 页码: 4929-4937
作者:
H. X. Hu
;
S. L. Jiang
;
Y. S. Tao
;
T. Y. Xiong
;
Y. G. Zheng
Adobe PDF(1360Kb)
  |  
收藏
  |  
浏览/下载:143/0
  |  
提交时间:2012/04/13
Large Powder Particles
Composite Coatings
Slurry Erosion
Kinetic
Spray
Liquid Impact
Alloy
Microstructure
Steels
Deposition
Resistance
Comparison of Inconel 625 and Inconel 600 in resistance to cavitation erosion and jet impingement erosion
期刊论文
Nuclear Engineering and Design, Nuclear Engineering and Design, 2010, 2010, 卷号: 240, 240, 期号: 10, 页码: 2721-2730, 2721-2730
作者:
H. X. Hu
;
Y. G. Zheng
;
C. P. Qin
Adobe PDF(3095Kb)
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收藏
  |  
浏览/下载:111/0
  |  
提交时间:2012/04/13
Stress-corrosion Cracking
Stress-corrosion Cracking
Aluminide Intermetallic Alloys
Aluminide Intermetallic Alloys
High-purity
High-purity
Water
Water
Mechanical-properties
Mechanical-properties
Crevice Corrosion
Crevice Corrosion
Solid Particles
Solid Particles
Wear
Wear
Behavior
Behavior
Microstructure
Microstructure
Deformation
Deformation
Steam
Steam
Acoustic emission of fatigue crack in pressure pipe under cyclic pressure
期刊论文
Nuclear Engineering and Design, 2010, 卷号: 240, 期号: 10, 页码: 3616-3620
作者:
Q. O. Ai
;
C. X. Liu
;
X. R. Chen
;
P. He
;
Y. Wang
Adobe PDF(703Kb)
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收藏
  |  
浏览/下载:95/0
  |  
提交时间:2012/04/13
Transition
Phase
Glass
Effects of loading factors on environmental fatigue behavior of low-alloy pressure vessel steels in simulated BWR water
期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2007, 卷号: 237, 期号: 12-13, 页码: 1452-1459
作者:
Wu, Xinqiang
;
Han, Enhou
;
Ke, Wei
;
Katada, Yasuyuki
收藏
  |  
浏览/下载:69/0
  |  
提交时间:2021/02/02