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钱桂安 [7]
Tong ZF [3]
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Creator:钱桂安
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Effect of environmental media on the fatigue property of Chinese A508-3 steel of AP1000
期刊论文
INTERNATIONAL JOURNAL OF FRACTURE, 2022, 卷号: 234, 期号: 1-2, 页码: 263-272
Authors:
Ning, Guangsheng
;
Zhong, Weihua
;
Li JH(李江华)
;
Cong, Tao
;
Sun JY(孙经雨)
;
Wang, Hui
;
Qian GA(钱桂安)
;
Berto, Filippo
Adobe PDF(1424Kb)
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View/Download:289/71
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Submit date:2021/11/01
Reactor pressure vessel steel
Primary coolant environment
Low cycle fatigue
Corrosion fatigue
Environmental fatigue correction factor
Temperature effect on fracture toughness of CLF-1 steel with miniature three-point bend specimens
期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 531, 页码: 7
Authors:
Xie Y
;
Peng L
;
Zhang WZ
;
Liao HB
;
Qian GA(钱桂安)
;
Wan YX
Adobe PDF(2128Kb)
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View/Download:268/119
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Submit date:2020/05/18
RAFM steel
Fracture toughness
Temperature effect
CLF-1
Fatigue model of domestic 316LN steel in simulated primary coolant environment of CAP1400
期刊论文
INTERNATIONAL JOURNAL OF FATIGUE, 2020, 卷号: 130, 页码: 6
Authors:
Zhong WH
;
Qian GA(钱桂安)
;
Tong ZF
;
Wu WW
;
Zhu SP
;
Wang CL
Adobe PDF(716Kb)
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View/Download:548/99
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Submit date:2020/03/21
Primary coolant pipe
Low cycle fatigue
Corrosion fatigue
Fatigue model
Environmental fatigue life
Fatigue model of domestic 316LN steel in simulated primary coolant environment of CAP1400
会议论文
19th International Colloquium on Mechanical Fatigue of Metals (ICMFM), Univ Porto, Fac Engn, Porto, PORTUGAL, SEP 05-07, 2018
Authors:
Zhong,Weihua
;
Qian GA(钱桂安)
;
Tong,Zhenfeng
;
Wu,Wenwang
;
Zhu,ShunPeng
;
Wang,Chenglong
Adobe PDF(716Kb)
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View/Download:134/57
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Submit date:2022/11/24
Primary coolant pipe
Low cycle fatigue
Corrosion fatigue
Fatigue model
Environmental fatigue life
Modelling of reactor pressure vessel subjected to pressurized thermal shock using 3D-XFEM
期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2019, 卷号: 353, 页码: 13
Authors:
Mora DF
;
Niffenegger M
;
Qian GA(钱桂安)
;
Jaros M
;
Niceno B
View
  |  
Adobe PDF(5171Kb)
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View/Download:358/103
  |  
Submit date:2019/11/26
Pressurized thermal shock
Large Break LOCA
Stress intensity factor
Reactor pressure vessel
Fracture mechanics
XFEM
A Statistical Model of Cleavage Fracture Toughness of Ferritic Steel DIN 22NiMoCr37 at Different Temperatures
期刊论文
MATERIALS, 2019, 卷号: 12, 期号: 6, 页码: 12
Authors:
Qian GA(钱桂安)
;
Lei WS
;
Tong ZF
;
Yu ZS
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Adobe PDF(3638Kb)
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View/Download:217/53
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Submit date:2019/05/29
statistical model
ferritic steels
cleavage fracture toughness
master curve behavior
Irradiation effect on impact fracture behavior of A508-3 steel in ductile-to-brittle transition range
期刊论文
ENGINEERING FAILURE ANALYSIS, 2019, 卷号: 97, 页码: 836-843
Authors:
Zhou ZY
;
Tong ZF
;
Qian GA(钱桂安)
;
Zhong WH
;
Wang CL
;
Yang W
;
Berto F
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  |  
Adobe PDF(1120Kb)
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View/Download:465/96
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Submit date:2019/04/11
Reactor pressure vessel
Neutron embrittlement
Crack propagation
Plastic deformation
Charpy impact test
Scanning electron microscopy