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Effect of Normal Force on Fretting Wear Behavior of Zirconium Alloy Tube in Simulated Primary Water of PWR
期刊论文
ACTA METALLURGICA SINICA-ENGLISH LETTERS, 2022, 页码: 16
Authors:
Zhang, Yusheng
;
Lai, Jiang
;
Ming, Hongliang
;
Gao, Lixia
;
Wang, Jianqiu
;
Han, En-Hou
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View/Download:7/0
  |  
Submit date:2023/05/09
Zirconium alloy tube
Fretting wear
Grid-to-rod
High-temperature pressurized water
Normal force
Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking
期刊论文
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2022, 卷号: 113, 页码: 229-245
Authors:
Wu, Bin
;
Ming, Hongliang
;
Meng, Fanjiang
;
Li, Yifeng
;
He, Guangqing
;
Wang, Jianqiu
;
Han, En-Hou
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View/Download:53/0
  |  
Submit date:2022/07/01
Alloy 690TT
Scratch
Surface
Stress corrosion
High temperature corrosion
Intergranular corrosion
Reaction Mechanism of High-Temperature Corium Pool of Core
期刊论文
RARE METAL MATERIALS AND ENGINEERING, 2022, 卷号: 51, 期号: 3, 页码: 913-920
Authors:
Xue Baoquan
;
Yang Yaqian
;
Liang Tian
;
Chen Bo
;
Ma Yingche
;
Liu Kui
;
Shan Hongyi
;
Kang Taifeng
;
Gu Peiwen
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  |  
View/Download:62/0
  |  
Submit date:2022/07/01
nuclear power safety
severe accident
in-vessel corium retention
molten zirconia
stratification mechanism
Effect of Dilution Ratio of the First 309L Cladding Layer on the Microstructure and Mechanical Properties of Weld Joint of Connecting Pipe-Nozzle to Safe-End in Nuclear Power Plant
期刊论文
ACTA METALLURGICA SINICA, 2020, 卷号: 56, 期号: 8, 页码: 1057-1066
Authors:
Zhang Maolong
;
Lu Yanhong
;
Chen Shenghu
;
Rong Lijian
;
Lu Hao
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  |  
View/Download:94/0
  |  
Submit date:2021/02/02
buttering welding
dilution ratio
microstructure
mechanical property
cracking mechanism
Microstructure of a domestically fabricated dissimilar metal weld joint (SA508-52M-309L-CF8A) in nuclear power plant
期刊论文
MATERIALS CHARACTERIZATION, 2019, 卷号: 148, 页码: 100-115
Authors:
Ming, Hongliang
;
Zhang, Zhiming
;
Wang, Jianqiu
;
Han, En-Hou
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  |  
View/Download:80/0
  |  
Submit date:2021/02/02
Dissimilar metal weld joint
GTAW
Microstructure
Duplex stainless steel
Nuclear power plant
Design of single-phase high-entropy alloys composed of low thermal neutron absorption cross-section elements for nuclear power plant application
期刊论文
INTERMETALLICS, 2019, 卷号: 104, 页码: 143-153
Authors:
Xiang, C.
;
Han, E-H
;
Zhang, Z. M.
;
Fu, H. M.
;
Wang, J. Q.
;
Zhang, H. F.
;
Hu, G. D.
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View/Download:115/0
  |  
Submit date:2021/02/02
High-entropy alloys
Alloy design
Mechanical properties
Nuclear power plant
Accident tolerant fuel
某核电厂楔形闸板阀阀瓣表面司太立合金堆焊层失效分析
期刊论文
腐蚀科学与防护技术, 2019, 卷号: 31.0, 期号: 006, 页码: 622-630
Authors:
张敏
;
明洪亮
;
王凡
;
张志明
;
王俭秋
;
韩恩厚
;
吕群贤
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  |  
View/Download:94/0
  |  
Submit date:2021/02/02
失效分析
司太立合金
堆焊层
阀瓣
Precise Determination of Trace Hydrogen in SA508-3 Steel for Nuclear Reactor Pressure Vessels
期刊论文
SCIENCE OF ADVANCED MATERIALS, 2018, 卷号: 10, 期号: 11, 页码: 1651-1657
Authors:
Hao, Luhan
;
Zhao, Wei
;
Peng, Yan
;
Sun, Mingyue
;
Li, Dianzhong
;
Liu, Hu
;
Wang, Xiaojing
;
Umar, Ahmad
;
Guo, Zhanhu
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View/Download:80/0
  |  
Submit date:2021/02/02
Determination
Trace Hydrogen
SA508-3 Steel
Nuclear Reactor Pressure Vessels
Evaluation of Fatigue Properties of CA6NM Martensite Stainless Steel Using Miniature Specimens
期刊论文
ACTA METALLURGICA SINICA, 2018, 卷号: 54, 期号: 10, 页码: 1359-1367
Authors:
Ma Yefei
;
Song Zhuman
;
Zhang Siqian
;
Chen Lijia
;
Zhang Guangping
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  |  
View/Download:75/0
  |  
Submit date:2021/02/02
martensite stainless steel
fatigue property
miniature specimen
size effect
nuclear power material
Research Progress on Sulfur-Induced Corrosion of Alloys 690 and 800 in High Temperature and High Pressure Water
期刊论文
ACTA METALLURGICA SINICA, 2017, 卷号: 53, 期号: 12, 页码: 1541-1554
Authors:
Xia Dahai
;
Song Shizhe
;
Wang Jianqiu
;
Luo Jingli
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  |  
View/Download:65/0
  |  
Submit date:2021/02/02
steam generator
alloy 690
alloy 800
thiosulfate
reduced sulfur
passive film