Concept of accident tolerant fuel in nuclear reactors
Krishna Kumar Yadav, Usha Pal, R. Karthikeyan
Topics & Concepts
Cladding (metalworking)Materials scienceZirconiumAlloyZirconium alloyLight-water reactorCoolantNuclear engineeringNuclear fuelFission productsMetallurgyAustenitic stainless steelFuel element failureAusteniteSpent nuclear fuelCorrosionMechanical engineeringEngineeringMicrostructureNuclear Materials and PropertiesNuclear reactor physics and engineeringFusion materials and technologies