Abstract
There exists a large body of publications on neutronics or thermal-fluids analyses of a prismatic gas-cooled reactor core. They mainly focus on stand-alone analyses, although the neutronics and thermal-fluids behavior affect each other. In order to consider the interaction between the neutronics and thermal-fluids behavior, a coupled analysis is desirable. However, only a few studies are available in the open literature on the coupled analysis of a prismatic gas-cooled reactor core. In this work, a code system for a coupled neutronics and thermo-fluids simulation was developed using CAPP (reactor physics code) and GAMMA+ (thermo-fluid system code). Using the code system developed, coupled neutronics and thermo-fluid simulations were carried out for a prismatic very high temperature reactor (VHTR) core to extend the knowledge about the coupled behavior. In particular, the effect of the bypass flow modeling on the coupled behavior was analyzed.
Published Version
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