Development and validation of Burn-up Calculation Code IMPC-Burnup2.0 for accelerator-driven sub-critical system
Zelong Zhao, Yongwei Yang, Qingyu Gao
Topics & Concepts
BurnupNuclear transmutationNuclideNuclear engineeringNeutron fluxNuclear physicsPhysicsNeutronComputer scienceEngineeringNuclear reactor physics and engineeringNuclear Materials and PropertiesFusion materials and technologies