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 …

Abstract System thermal-hydraulic (STH) codes are based on 1D lumped parameter
approach, which has limited capabilities to model 3D flow mixing phenomena. To close this …

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

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 …

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 …

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

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

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 …

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

The THINS project of the 7th Framework EU Program on nuclear fission safety is devoted to
the investigation of crosscutting thermal–hydraulic issues for innovative nuclear systems. A …