|About this Abstract
||7th World Congress on Integrated Computational Materials Engineering (ICME 2023)
||Modelling of carbides in irradiated steel microstructure
||Andris Freimanis, Matti Lindroos, Anssi Laukkanen, Sicong Ren
|On-Site Speaker (Planned)
This paper explore ICME workflow that enables the virtual design of radiation resistant materials. Carbides, solute clusters, and dislocation loops are a critical microstructure/material features of reactor pressure vessel steel. Irradiation generates these defects, which contribute to reduction of ductility and the ductile-to-brittle transformation of metals used in fission or future fusion power plants. In this paper, authors' consider the fracture in unirradiated and irradiated microstructures of reactor pressure vessel steel. Finite-element simulation results are compared with peridynamic theory’s results to address key features like defect size effect. Several cases of intragranular and intergranular fractures are presented.
||Planned: Other (describe below)