Thermochemically-informed mass transport model for interdiffusion of U and Zr in irradiated U-Pu-Zr fuel with fission products
Max Poschmann, M.H.A. Piro, Theodore M. Besmann, Kevin Clarno, Srdjan Simunovic
Topics & Concepts
BurnupFission productsNuclear fission productFissionNuclear fuelFissile materialSpent nuclear fuelNuclear engineeringChemistryIrradiationMetalRedistribution (election)MOX fuelMaterials scienceNuclear physicsRadiochemistryThermodynamicsNuclear chemistryMetallurgyPhysicsNeutronPlutoniumPoliticsEngineeringLawPolitical scienceNuclear Materials and PropertiesNuclear reactor physics and engineeringFusion materials and technologies