SUMMARY
Long-term radiation exposure is certain for materials with applications in next-generation nuclearreactors, and consequentially, the study of aging of materials has been a popular topic of researchfor decades, as a crucial part of safer reactor designs. At the atomic scale, radiation damagesare the results of numerous displacement cascade events, initiated by high energy particle collisions. An individual displacement event creates vacancy-interstitial point defect pairs knownas Frenkel Pair/defect (FP) in the material lattice. The diffusion and accumulation of the vacancypoint defects form larger voids; similarly, the interstitial defect buildup forms various structural dependent dislocation loops and, in f.c.c. lattice, stacking-fault tetrahedra. Withsufficient defect concentrations in the bulk, amorphization can also be observed in materialswith weakened lattices. In most materials, crystalline grain and phase boundaries act as potentdefect sinks, trapping defects and fission gases alike. The presence and accumulation ofvoid defects and fission gases tend to weaken grain/phase boundary bonding, eventually leading toboundary decohesion or formation of micro-cracks. In turn, the growth rates of existingmicro-cracks are affected by the emission of dislocation defects and microstructure variations onthe boundary, although the net effects are still ambiguous. Obviously grain and phaseboundaries interactions with the various aforementioned processes play key roles in the aging process. Atomistic scale models are the logical tools to study the boundary aging phenomena, havingthe capability to directly simulate boundary microstructures, collisional cascade damages and pointdefect evolutions.For this project, variations of Silicon Carbide phase boundaries are chosen as the case study.The high melting point and low oxidation rate of SiC makes it a favorable choice for fuel claddingin next-gen reactors and structural material in fusions operations. Both applications resultin harsh radiation exposure during its lifetime. Although considered a brittle ceramic material,SiC has been observed to exhibit metallic plasticity behaviors in nano-scale deformations. Thisallows access to the atomistic study of decohesion crack growth mechanisms