Validation of a VVER 1000 Trace Model

The presented article discusses developing and validation of a VVER 1000 TRACE V5.0p5 model. Developing such model for computer code is important as it increases the capability analyses in simulating nuclear power plant behaviour different accidents including capabilities 3D thermal hydraulic phenomena reactor core simultaneously with physics calculations. In this way, possible to conduct transients involving spatial thermal-hydraulic processes core. an existing RELAP5 1D has been used developed INRNE-BAS widely validated safety assessment system. process includes comparisons steady-state transient selected parameters calculated from Mod3.3 compared results received by using new integral response system during total station blackout (SBO) event investigated. shutdown system, isolating turbine, transition forced natural circulation coolant primary circuit, switching off feed water all steam generators (SGs), activation valves secondary circuits, dryout SGs, loss circulation, heat up, etc. performed comparison shows very good agreement between