Journal of Nuclear Science and Technology · 2007 · 11 citations · 1 references
EngineeringComputational EngineeringNuclear EngineeringComputational MechanicsHydraulicsReactor PhysicsNeutron Transport TheoryReactor Core DesignReactor DynamicsReactor KineticsThermal Reactor PhysicsDrift-flux ModelNeutronic-thermal-hydraulic CouplingRod Ejection TransientsSystem-scale Transient AnalysisThermal-hydraulic Code ValidationThermal-hydraulic CodesThermal-hydraulic CouplingThree-dimensional Core Modeling
Three-dimensional (3D) neutronics and thermal-and-hydraulics (T/H) coupling code, ANCK/MIDAC, has been developed. ANCK/MIDAC consisted of the 3D nodal kinetic code ANCK and the 3D drift flux T/H code MIDAC. In order to verify the adequacy of ANCK that is a kinetics engine of this coupling code, several international benchmark problems have been performed. The calculation results of LMW (Langenbuch, Maurer and Werner) benchmark problems, PWR rod ejection benchmarks and PWR benchmarks on uncontrolled withdrawal of control rods at zero power are shown in this paper. The comparison of the results with the reference solutions shows very good agreements with the main core parameters.
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