Neutron irradiation-induced microstructure damage in ultra-high temperature ceramic TiC

Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation

“…Energetic particles can knock atoms out of their lattice site and create point defects (vacancies, interstitials). These point defects can evolve into extended defects such as dislocation loops, cavities, or stacking fault tetrahedra [11][12][13][14][15]. In some cases, element segregation, phase transition and chemical interactions can be induced by irradiation [16][17][18][19][20].…”

A combined theoretical-experimental investigation of thermal transport in low-dose irradiated thorium dioxide

“…The rel-rod dark field technique imaging technique was employed to image Frank loops present in the microstructure, following the procedure described previously [20] for characterizing dislocation loops in ThO2 crystals irradiated with protons to higher doses. This technique has been widely applied for characterizing microstructural features in irradiated face-centered-cubic materials [45][46][47][48]. The size and areal density distribution of the dislocation loops was determined from the dark field images using manual image analysis using ImageJ software [49].…”

Compositionally complex carbide ceramics: A perspective on irradiation damage

“…Voids were not reported in irradiation-induced microstructures in most reports of transitional metal monocarbides such as ZrC and TiC. 26 Small voids (∼5 nm) were only observed after neutron irradiation at extremely high temperatures and dose (1496 °C, 5.8 × 10 25 N/m 2 , E > 0.1 MeV), but the number density of these voids was extremely low. The absence of void swelling in ZrC may be explained by the ab initio calculations that suggested that Zr and C vacancies have high migration energy barriers resulting in a low mobility of vacancies.…”

“…FIG.2. Summary of the literature data for the quantitative evaluation of the irradiation damage in the CCC: (a) lattice parameter expansion; (b) dislocation loop diameter; and (c) irradiation-induced hardness increase as a function of irradiation temperature and dose 22,26,[37][38][39][40]. The filled symbols are for CCC, while the open symbols are for monocarbides.…”