SIMULATION OF THE FIRST-LOOP WATER CHEMISTRY REGIME OF A NUCLEAR POWER SYSTEM WITH A TWO-PHASE WATER COOLANT

摘要

An approach to simulating the water-chemistry regime for transient and stationary operating states of a nuclear power system is proposed. The approach is based on the designer's philosophy. The first loop of the nuclear power system is divided into standard units. The special features of the reactor design and the crux of the problem being solved determine the number of units and the interaction between them. The units can be structural components of the loop as well as coolant components. The thermochemical and radiation-chemical transformations of the components of the water coolant are simulated at each unit. The interaction between the physicochemical processes at the units is expressed in the flow of the coolant components between them. The approach developed is illustrated on the analysis of the water-chemistry regime in implementing a passive safety system - a promising solution geared toward increasing the operational safety of the first loop of a nuclear power system.