Thermohydraulic Calculation of VVER and SCWR Reactor Channels

摘要

The results of a comparative thermohydraulic calculation of the core channels of two types of nuclear reactors – VVER and VVER-SKD, differing in the coolant parameters at the inlet to the core channel – are presented. It was established that at the identical thermal power the maximum temperature at the center of a VVER-SKD fuel element is lower than that of a VVER fuel element.