Comparative neutronics analysis of DIMPLE S06 criticality benchmark with contemporary reactor core analysis computer code systems

Keyphrases

• Comparative Analysis 100%
• Modeling Approach 100%
• Coding System 100%
• Computer Code 100%
• Reactor Core Analysis 100%
• Neutronic Analysis 100%
• Two-scale Homogenization 100%
• Criticality Assessment 100%
• Flux Distribution 50%
• Monte Carlo Code 50%
• Challenging Problems 50%
• Scattering Effect 50%
• Two-step Approach 50%
• Small Core 50%
• Homogenization Method 50%
• Power Distribution 50%
• Anisotropic Scattering 50%
• Neutronic Parameters 50%
• Multiplication Factor 50%
• Homogenized Cross Sections 50%
• Calculation Procedure 50%
• Transport Approximation 50%
• Core Design 50%
• Mcnp 50%
• Transport Cross Section 50%
• Heterogeneous Approach 50%
• Heterogeneous Modeling 50%
• Assembly Interface 50%
• Lattice Physics Code 50%
• Homogenization Modeling 50%
• Serpent 2 50%

Engineering

• Cross Section 100%
• Comparative Analysis 100%
• Reactor Core 100%
• Core Analysis 100%
• Neutronic Analysis 100%
• Anisotropic 50%
• Scattering Effect 50%
• Step Approach 50%
• Power Distribution 50%
• Neutronics 50%
• Multiplication Factor 50%
• Smaller Core 50%
• Calculation Procedure 50%