Fission recoil-induced microstructural evolution of the fuel-cladding interface [FCI]in high burnup BWR fuel

Keyphrases

• After Service 33%
• Equilibrium Temperature 33%
• Fission 100%
• Fission Products 33%
• Fuel Cladding 33%
• Grain Growth 33%
• High Burnup 100%
• Interface Region 33%
• Light Water Reactor 33%
• Metal Particles 33%
• Microstructural Evolution 100%
• Monoclinic Phase 33%
• Nuclear Cladding 33%
• Nuclear Fuel 33%
• Oxidation Behavior 33%
• Oxidation-reduction 33%
• Oxide Interfaces 33%
• Performance Prediction 33%
• Phase-only 33%
• Radiation Damage 33%
• Structural Evolution 33%
• Structural Reduction 33%
• Tetragonal Phase 66%
• Zirconium Dioxide 66%

Engineering

• Burnup 100%
• Cross Section 50%
• Equilibrium Temperature 50%
• Fission Product 50%
• Light Water Reactors 50%
• Microstructural Evolution 100%
• Monoclinic 50%
• Radiation Effect 50%

Material Science

• Metal Product 50%
• Microstructural Evolution 100%
• Nuclear Fuel 50%
• Oxidation Reaction 50%
• Oxide Interface 50%
• Radiation Damage 50%
• Zirconia 100%