Assessment of the nuclear power plant behaviour during a small break LOCA combined with a SGTR assuming a station black out

This paper presents the comparison of the results achieved by performing calculations using integral computer codes RELAP5/mod3.3 and TRACEv5.05. The scenario selected for this purpose is a multiple failure transient based on a “Small break loss of coolant accident (SB LOCA) combined with a steam generator tube rupture (SGTR) simultaneously with a Station blackout (SBO)”. In the investigated scenario is assumed that the break with equivalent diameter of 30 mm is located on the main coolant loop #1 between the main coolant pump and the inlet of the reactor vessel. In addition, a double ended guillotine tube rupture in SG #4 with the equivalent diameter of 13 mm is simulated simultaneously with a SBO.
The main objective of this work is focused on evaluation of VVER1000 plant response during multiple failure events and the ability of system thermal hydraulic computer codes to simulate the key phenomena and processes taking place during the evolution of the accidental scenario.
The computer codes used to perform the study are based on different approach for the modeling of the reactor pressure vessel (RPV) and core physics. The RELAP5 code is based on 1D thermal hydraulics modelling of RPV and point kinetics for reactor physics modelling, while in the TRACE code used 3D thermal hydraulics of RPV modelling and 3D neutron kinetics model for reactor physics modelling. ... mehrThe calculation is performed for the end of cycle (EOC) eight, when the reactor is operated at nominal power.
The investigations were performed in the frame of the EU H2020 CAMIVVER project. The comparison of the calculated results has shown that the codes predict the VVER1000 plant behavior under SB LOCA with SGTR simultaneously with a SBO in a good manner.