Abstract and subjects
Stress corrosion cracking (SCC) is a significant concern for nuclear reactor technology, notably for higher burn-up conditions. At the pellet-cladding interface (PCI), the surface of the interior oxide layer is subject to not only pressures, but also chemically reactive species from evolved fission gases. Existing cumulative damage index models (CDI) are almost entirely empirical-based[1]; therefore, significant room for improvement can be made in regards to reactor and fuel performance codes. Further, a recent publication by Lewis et al.[2] discussed iodine-induced stress corrosion cracking, but assumes an incubation time as a constant regardless of conditions. The purpose of this ongoing research is to study the initiation stages of ISCC, which are poorly understood. [3-4]