Thermal hydraulic system o f a V V ER-1000 nuclear reactor and numerical simulations

Abstract

This paper presents som e results of our study on the numerical simulation of the thermal hydrauric system of the Russian VV E R -1000 pressurized w ater nuclear reactors. The sim ulations were co n d u cted using the integrated VISA (V isual System A nalyzer) and R ELA P5 (R eactor Excursion and Leak A nalysis Program ,version 5) softw ares know n as V ISA _R E L A P5. Originally RELA P5 (a therm al hydraulic system code) and then recently V ISA (a graphical user interface) were d ev elo p ed for the simulation o f the therm alhydraulic system o f W estern type pressurized w ater reacto rs (P W R ) undergoing transients. In V ietnam , research on the num erical sim ulation of the therm al hy d rau lic system o f Da Lat nuclear research reactor and som e typical types o f PWRs using R E L A P 5 h av e long been carried out in our research group along w ith som e o f other research institutions. It should be noted th at know ledge o f the V V E R reactor system is still lacking in Vietnam until now. The data that we used in our modelings, simulations and calculations are real data o f the K alinin nuclear pow er plant (N PP) in Russia. T herefore this research has im portant practical im p licatio n s especially for the p reparation for the safe operation and pro p er m anagem ent o f in cidents (accid en ts) in the N P P that w ill be built in N inh T huan, V ietnam . The reactors adopted in the Ninh Thuan NPP will be the Russian VVER PWR. From the point of view of the available information about VVER reactors in Vietnam, our study is immensely useful since Russia has not yet much opened up infomiation about W E R reactors. At this point, our research is a b asic im p o rtan t step tow ards a practical study case.