Analysis of thermal–hydraulic parameters of WWER-1000 containment in a large break LOCA

Highlights: • Evaluation +98 of WWER-1000 containment behavior against LBLOCA accident. • Simulation of WWER-1000 containment by CONTAIN 2.0 code. • Modeling of WWER-1000 containment by a single model. • Validation of results with Bushehr Nuclear Power Plant's FSAR. - Abstract: The consequences of sever reactor accident depend greatly on containment safety features and containment performance in retaining radioactive material. The specific type of large LOCA is DECL (Double Ended Cold Leg) break which means a total guillotine type of break in cold leg pipe and is one of the most dangerous accidents in the reactor containment. In this paper, thermal–hydraulic parameters (temperature and pressure) of WWER-1000 (Bushehr Nuclear Power Plant) containment in a DECL accident have been simulated by CONTAIN 2.0 code and a single cell model. The containment has been divided to 23 cells in CONTAIN code but for simplicity only one cell has been considered in modeling. The model has been programmed by MATLAB. The accident has been simulated for a short time (initial 200 s) and all of the results have been compared with Bushehr's Nuclear Power Plant FSAR