Simulation is becoming increasingly important in the safety analysis of nuclear reactors
nowadays. The physical phenomena in a nuclear power plant happen on three classified …

This paper investigates the use of the Functional Mock-up Interface (FMI) for code coupling
in nuclear engineering. The FMI is a standard that defines a container and an interface to …

Application of coupled CFD (Computational Fluid Dynamics) and STH (System Thermal
Hydraulics) codes is a prerequisite for computationally affordable and sufficiently accurate …

This work aims to review the general guidelines to be adopted to perform coupled System
Thermal Hydraulics (STH)/CFD calculations. The coupled analysis is often required when …

The paper describes the development and validation of a coupling methodology between
the best-estimate system thermal-hydraulic code RELAP5-3D and the CFD code FLUENT …

A novel multiscale coupling methodology based on a domain overlap** approach has
been developed to couple a computational fluid dynamics code with a best-estimate thermal …

Abstract Design and safety analysis of the currently developed pool type liquid metal cooled
fast nuclear reactors is currently impaired by limited operational experience for such systems …

The system thermal-hydraulic (STH) code ATHLET was coupled with the commercial 3D
computational fluid dynamics (CFD) software package ANSYS CFX to improve ATHLET …

Within the MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications)
project, the Belgian Nuclear Research Centre SCK• CEN is develo** and designing a …

Abstract In a Nuclear Power Plant (NPP), the Thermal-Hydraulic (TH) phenomena take place
at different scales in the core and the primary and secondary circuits. Thus different TH …