RELAP5-CFX COUPLING MODULE: TESTING ON SIMPLE THERMOHYDRAULIC MODELS

The modern direction in the study of safety nuclear power plants is to ensure maximum level detail process modeling with a satisfactory computational resources. One approaches such task solving coupled use special software required levels detail, for example, systemic thermohydraulic codes hydrodynamics codes.
 This article describes developed coupling module between system code RELAP5/Mod. 3.2 and CFX code, using an external explicit interfacing scheme without overlap, which acts as main RELAP5 secondary one. development this part work on integrated severe accidents makes it possible model defining processes phenomena that occur during accident within reactor vessel CFD model, elements unit acceptable cost resources high detail. To check technology, was tested simplified models containing serially connected RELAP5- CFD-models horizontal pipes, well closed loop. In view further interface full-fledged VVER-1000, testing performed three types: "input flow", "output flow" their combination "input/output After completion testing, accuracy credibility results calculations evaluated by comparing them autonomous calculations. Results tests support possibility RELAP5-CFX more complex large-scale models.