On the Use of Chromium Coating for Inner-Side Fuel Cladding Protection: Thickness Identification Based on Fission Fragments Implantation and Damage Profile

Inner-side coatings have been proposed as a complementary solution within the accident tolerant fuel (ATF) framework, to provide enhanced protection for nuclear cladding. Unlike external surface, degradation of irradiated internal cladding surface has not studied extensively. Fission fragments produced during fission is one key players in this degradation. This study aimed estimate minimum thickness thin chromium film, required protect inner side The approach used based on set calculations, Ion ranges and damage profiles, group fragments, using TRIM code. calculation results were verified by comparison with experimental data associated phenomena thermo-releasing elements. recommended such film was found be 9 microns. Calculations also showed that metal greater stopping power compared zirconium-based alloy E110, which indicates an increased ability withstand exposure energetic reactor operation.