4:40 PM - 4:55 PM
[1C08] Study on Material Properties Changes and Fracture Modes for BWR Internal Components under Neutron Irradiation
Keywords:Reactor Internal Components, Irradiation Assisted Stress Corrosion Cracking, Neutron Irradiation, Austenitic Stainless Steel, Fracture Evaluation, Linear-Elastic Fracture Mechanics, Elastic-Plastic Fracture Mechanics, Structural Integrity
In the technical evaluation of Plant Life Management (PLM), structural integrity evaluations are required for the degradation mechanisms expected for the subject equipment and components. The methods and criteria provided for the fracture evaluation in structural integrity evaluation for Irradiation Assisted Stress Corrosion Cracking (IASCC) of Boiling Water Reactor (BWR) internal components have been developed conservatively based on linear-elastic fracture mechanics, considering the decrease in ductility due to neutron irradiation.
In this study, applicability of fracture evaluation methodology based on the elastic-plastic fracture mechanics was investigated for a core shroud with an IASCC. The fracture mode evaluations with failure assessment diagram were performed by using the material properties of irradiated austenitic stainless steels, which vary with increasing neutron fluence.
In this study, applicability of fracture evaluation methodology based on the elastic-plastic fracture mechanics was investigated for a core shroud with an IASCC. The fracture mode evaluations with failure assessment diagram were performed by using the material properties of irradiated austenitic stainless steels, which vary with increasing neutron fluence.