2022-04-06 08:00:00
There has been considerable interest in chemical vapor infiltration (CVI) manufactured silicon carbide fiber and silicon carbide matrix (SiC/SiC) composite tubes due to their superior mechanical properties. The SiC/SiC tubes are known to remain stable even after prolonged exposure to radiation. However, there are…
Dislocation-obstacle interactions are established as an effective strengthening mechanism within metallic materials. Several example material systems include Mg and Al alloys as well as those found in nuclear reactors. In each of these systems, the unit process governing material strength is the bypass of…
We present molecular dynamics simulations of plastic deformation of nickel (Ni) containing nano-scale helium bubbles. Defect structures in our model are built basing on experimental data of ex-service Ni-based alloy components in pressurized heavy water reactors. Dislocation nucleation and motion, slip band formation and…
Materials with modified surfaces – either as a consequence of a graded microstructure, or due to an intentional alteration of the surface – are of increasing interest for a variety of applications ranging from enhanced wear and corrosion resistance, superior thermal and biomedical properties,…
The Nuclear Technology R&D program has significant experience at qualifying metallic fuels for fast reactor applications. In this process, new fuels and cladding materials must be developed and tested to high burnup levels (e.g. >20%) requiring cladding to withstand very high doses (greater than…
This talk will illustrate the effects of irradiation defect microstructures on low temperature localized deformation mechanisms, specifically twinning and martensitic phase transformations, in face centered cubic (fcc) alloys. The presence of irradiation-induced point defects, dislocation loops, and voids, can have a profound effect on…
