To predict the thermal hydraulic behavior in nuclear power plants, traditional system codes
such as RELAP, MARS, and CATHARE, designed for one-dimensional two-phase flows …

The analysis of nuclear reactors for performance and safety assessment benefits from the
use of computational tools. In this context, this work aims at the development and application …

Traditional 1D system thermal hydraulic analysis has been widely applied in nuclear
industry for licensing purposes due to its numerical efficiency. However, such codes are …

This paper presents a numerical algorithm of the implicit coupling for a multi-scale thermal
hydraulic analysis developed with the specific application of integration of a component …

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 …

For the thermal hydraulics analysis of nuclear reactor components of LWRs (Light Water
Reactors) such as reactor vessel, steam generator, containment, a multi-dimensional two …

The system thermal-hydraulic code SPACE adopts a multidimensional two-fluid, three-field
model to simulate two-phase-flow phenomena encountered during various anticipated …

A multi-dimensional thermal-hydraulic analysis code called SPACE (Safety and
Performance Analysis Code for Nuclear Power Plant) is being developed by Korean nuclear …

A multi-dimensional realistic thermal-hydraulic system analysis code, MARS version 1.3 has
been developed. Main purpose of MARS 1.3 development is to have the realistic analysis …

There have been recent efforts to establish methods for high-fidelity and multi-physics
simulation with coupled thermal–hydraulic (T/H) and neutronics codes for the entire core of a …