Prediction of the effects of neutron irradiation on the Charpy ductile to brittle transition curve of an A508 pressure vessel steel

References

Page 1

	Year	Citations
A local criterion for cleavage fracture of a nuclear pressure vessel steel F. M. Beremin, A. Pineau, F. Mudry, Metallurgical Transactions A Materials ScienceCleavage FractureEngineeringMechanical EngineeringHigh Strength Low Alloy Steel	1983	1.2K
Ductile fracture models and their potential in local approach of fracture G. Rousselier Nuclear Engineering and Design EngineeringMechanicsMechanical EngineeringDynamic Crack PropagationSolid Mechanics	1987	707
The temperature and strain-rate dependence of the shear strength of mild steel J. D. Campbell, W. G. Ferguson Philosophical magazine EngineeringMechanical EngineeringRate SensitivityHigh Strength Low Alloy SteelStructural Steel	1970	421
Modeling of crack growth in round bars and plane strain specimens Jacques Besson, D. Steglich, W. Brocks International Journal of Solids and Structures Round BarsEngineeringStrain LocalizationMechanical BehaviorMechanics	2001	189
Numerical modeling of ductile crack growth in 3-D using computational cell elements Cláudio Ruggieri, TL Panontin, R.H. Dodds International Journal of Fracture Materials ScienceEngineeringDuctile Crack GrowthComputational Cell ElementsMechanics	1996	176
Ductile to brittle transition of an A508 steel characterized by Charpy impact test B. Tanguy, Jacques Besson, R. Piques, Engineering Fracture Mechanics Materials ScienceEngineeringSevere Plastic DeformationA508 SteelMechanical Engineering	2004	143
Radiation embrittlement of low-alloy steels Yu. A. Nikolaev, A. V. Nikolaeva, Ya. I. Shtrombakh International Journal of Pressure Vessels and Piping Materials ScienceMaterials EngineeringEngineeringRadiation EmbrittlementCorrosion	2002	46
Effect of microstructure on the susceptibility of a 533 steel to temper embrittlement Stephane Raoul, B. Marini, A. Pineau Journal of Nuclear Materials Materials ScienceEngineeringCorrosionMechanical EngineeringCold Working	1998	34
An extension of the Rousselier model to viscoplastic temperature dependent materials B. Tanguy, Jacques Besson International Journal of Fracture	2002	31
Effect of neutron flux on low temperature irradiation embrittlement of reactor pressure vessel steel K. Dohi, Takeo Onchi, Fumihisa Kano, Journal of Nuclear Materials EngineeringCorrosionMechanical EngineeringNeutron FluxNeutron Source	1999	15

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