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51314-4231-Effect of Yield Strength on Stress Corrosion Cracking Growth in Neutron-Irradiated Stainless Steels

Product Number: 51314-4231-SG
ISBN: 4231 2014 CP
Author: Yugo Ashida
Publication Date: 2014
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Effect of Alloy Yield Strength on Stress Corrosion Cracking Growth in Neutron-Irradiated Stainless SteelsYugo Ashida Peter L. Andresen Gary S. Was Mechanical properties such as yield strength and hardness of irradiated stainless steels can be significantly changed by increasing irradiation dose. To understand the effects of mechanical properties on crack growth in neutron-irradiated stainless steels is required for identifying irradiation assisted stress corrosion cracking (IASCC) mechanism and for establishing strategies for IASCC mitigation. In this study experimental crack growth rate (CGR) data of irradiated alloys reported by the University of Michigan and the Cooperative IASCC Research (CIR) program were correlated with hardness and yield strength as well as with microstructural and microchemical variables such as loops precipitates and Cr depletion and Si enrichment at grain boundaries. It was found the increase in CGR directly proportional to the increase in yield strength and hardness but not straightforwardly related to any other variables. On the other hand finite element method (FEM) will be conducted to estimate CGR by calculating plastic strain increase per unit crack length increase at a characteristic distance r0 ahead of the crack tip. Yield strengths 250 500 750 and 1000 MPa will be used to simulate those of stainless steels at different irradiation dose. An 8 mm round compact tension (RCT) specimen under constant K control at 15 MPa.m1/2 will be used for ABAQUS simulation. Experimental and simulation results on the CGRs of irradiated alloys will be compared. In addition the similarity and differences between cold work hardening and irradiation hardening will be discussed. 
Effect of Alloy Yield Strength on Stress Corrosion Cracking Growth in Neutron-Irradiated Stainless SteelsYugo Ashida Peter L. Andresen Gary S. Was Mechanical properties such as yield strength and hardness of irradiated stainless steels can be significantly changed by increasing irradiation dose. To understand the effects of mechanical properties on crack growth in neutron-irradiated stainless steels is required for identifying irradiation assisted stress corrosion cracking (IASCC) mechanism and for establishing strategies for IASCC mitigation. In this study experimental crack growth rate (CGR) data of irradiated alloys reported by the University of Michigan and the Cooperative IASCC Research (CIR) program were correlated with hardness and yield strength as well as with microstructural and microchemical variables such as loops precipitates and Cr depletion and Si enrichment at grain boundaries. It was found the increase in CGR directly proportional to the increase in yield strength and hardness but not straightforwardly related to any other variables. On the other hand finite element method (FEM) will be conducted to estimate CGR by calculating plastic strain increase per unit crack length increase at a characteristic distance r0 ahead of the crack tip. Yield strengths 250 500 750 and 1000 MPa will be used to simulate those of stainless steels at different irradiation dose. An 8 mm round compact tension (RCT) specimen under constant K control at 15 MPa.m1/2 will be used for ABAQUS simulation. Experimental and simulation results on the CGRs of irradiated alloys will be compared. In addition the similarity and differences between cold work hardening and irradiation hardening will be discussed. 
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