Burnup computations of multi-pass fuel loading scenarios in HTR-10 using a pre-generated fuel composition library
Jhao-Yang Hong, Shin-Rong Wu, Shang-Chien Wu, Der-Sheng Chao, Jenq‐Horng Liang
Topics & Concepts
BurnupNuclear engineeringFission productsSpent nuclear fuelEnvironmental scienceNuclear reactor coreFissionMaterials scienceEngineeringNuclear physicsPhysicsNeutronNuclear reactor physics and engineeringNuclear Materials and PropertiesGraphite, nuclear technology, radiation studies