On the validation and application of fluid–structure interaction analysis of reactor vessel internals at loss of coolants accidents

Abstract

This paper presents results from various numerical simulations using ADINA fluid–structure interaction capabilities in the Swedish nuclear industry. The purpose with the simulations is to determine reactor pressure vessel internals response due to rapid depressurization associated with a pipe break. The fluid has been either steam or water in the different analyses. This paper presents a short description of the validation against the HDR experiment and also some of the actual calculations that have been performed. Two models have been used to apply the method on real geometry with different fluid properties, steam and water. Hence, the applicability of the ADINA system to variations of physical behaviour of the fluid and model size is shown.