The lead-based reactor is one of the fourth-generation nuclear energy systems with
excellent development prospects. It has attracted much attention because of its unique …

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 …

The system code package AC 2 by GRS for safety analyses of nuclear reactors from normal
operation to severe accidents has been updated with a new release. We briefly describe the …

The growing interest in fast reactors demands further innovative technologies to enhance
their safety and reliability. Understanding thermal hydraulic activities required for advanced …

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 …

This work describes the coupling methodology between a modified version of
RELAP5/Mod3. 3 and ANSYS Fluent CFD code developed at the University of Pisa. The …

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 lead-bismuth eutectic (LBE) cooled fast reactor (LFR) has shown promising applications
due to its excellent neutron economy and thermal-hydraulic characteristics. Nevertheless …

This paper describes a multi-scale thermal–hydraulic coupling system, which combines the
capabilities of the open-source TrioCFD code and of the sub-channel code SubChanFlow …

Multi-scale coupling simulation can obtain both system characteristics and three-
dimensional flow field of complex structural components. Therefore, it is a significant method …