Numerical Study of Three-Dimensional Steam-Water Flows in Circulation Loops of VVER-type Reactors with Best Estimate Thermal Hydraulic Code BAGIRA

摘要

We present here three-dimensional best estimate thermal hydraulic code BAGIRA intended for comprehensive safety analysis of nuclear power plants. A system of basic equations underlying the physical model of the code, together with the method of their solution, are exposed. Some applications of the code BAGIRA to modeling three-dimensional flows in coolant circuits of nuclear power plants with VVER-type reactors are considered.