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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
CORROSION SCIENCE, 2018, 卷号: 132, 页码: 9-20
Authors:  Dong, LJ;  Peng, QJ;  Xue, H;  Han, EH;  Ke, W;  Wang, L;  Peng, QJ (reprint author), Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Liaoning, Peoples R China.
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Low-alloy Steel  High-temperature Water  Heat-affected Zone  Bwr Coolant Environments  Grain-boundary  Metal Weld  Assisted Cracking  Stainless-steel  Chromium Depletion  Residual-stress  
Modeling flow stress constitutive behavior of SA508-3 steel for nuclear reactor pressure vessels 期刊论文
Journal of Nuclear Materials, 2011, 卷号: 418, 期号: 1-3, 页码: 269-280
Authors:  M. Y. Sun;  L. H. Hao;  S. J. Li;  D. Z. Li;  Y. Y. Li
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Low-alloy Steels  Low-carbon Steel  Hot Deformation  Mechanical-properties  Fracture-toughness  Temperature  Austenite  Working  
Effects of dynamic strain aging on mechanical properties of SA508 class 3 reactor pressure vessel steel 期刊论文
Journal of Materials Science, 2009, 卷号: 44, 期号: 11, 页码: 2882-2889
Authors:  S. Xu;  X. Q. Wu;  E. H. Han;  W. Ke
Adobe PDF(704Kb)  |  Favorite  |  View/Download:342/144  |  Submit date:2012/04/13
High-temperature Water  316l Stainless-steel  Deformation-behavior  Tensile Properties  Activation-energy  Jerky Flow  Alloy  Fatigue  Fracture  Model  
Effects of strain rate and temperature on tensile behavior of hydrogen-charged SA508 Cl.3 pressure vessel steel 期刊论文
Materials Science and Engineering a-Structural Materials Properties Microstructure and Processing, 2003, 卷号: 348, 期号: 1-2, 页码: 309-318
Authors:  X. Q. Wu;  I. S. Kim
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Hydrogen Effects  Dynamic Strain Aging  Pressure Vessel Steel  Mechanical Properties  Assisted Ductile Fracture  Fatigue-crack-growth  Low-alloy Steel  Serrated Flow  Environment  Embrittlement  Carbon  Iron