Nuclear Technology · 1992 · 67 citations · 4 references
EngineeringComputational EngineeringNuclear EngineeringComputational Fluid DynamicsFluid DynamicsHeat TransferFlow ModelingFlow RegimesHeat Transfer AnalysisHydraulic ModelingMultiphase Flow SimulationTransient Flow AnalysisInterfacial Area TransportOperational TransientsPhase Interaction ModelingSteady-state FlowThermal-hydraulic CodesThermal-hydraulicsTwo-fluid ModelTwo-phase Flow Modeling
VIPRE‑02 is a thermal‑hydraulic analysis code for steady‑state and transient conditions in light‑water reactor cores and vessels. It models two‑phase flow with a two‑fluid, six‑equation formulation solved implicitly via a modified Gauss‑Seidel iteration, using subchannel equations, optional 3‑D lower‑plenum geometry, and empirical or dynamic flow‑regime models for phase interaction.
The VIPRE-02 code is a thermal-hydraulic analysis code designed to model steady-state conditions and operational transients in light water reactor cores and vessels. It uses a two-fluid representation of two-phase flow that solves conservation equations for mass, momentum, and energy for each phase. The code uses a subchannel formulation of the conservation equations but also contains an optional three-dimensional (r-θ coordinates) representation of the lower plenum for vessel modeling. The six-equation formulation is solved implicitly, by a modified Gauss-Seidel iteration procedure, and has no time step size limitation for stability. Models for phase interaction based on flow regime mapping are provided that use empirical models and correlations for heat and mass transfer at the interface and vapor generation. In addition, the code contains as an option a dynamic flow regime model, which uses an interfacial area transport equation to determine the phase interaction terms.
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