Thermal hydraulics of innovative nuclear system

Abstract

Thermal-hydraulics is recognized as a key scientific subject in the development of different innovative reactor and transmutation systems. In spite of the difference in coolants (gas, water and liquid metals) and flow channel structures formed by different fuel lattice arrangements, five crosscutting thermal-hydraulic issues are identified and selected in the THINS project, i.e.:

advanced reactor core thermal-hydraulics single phase mixed convection single phase turbulence multi-phase flow code coupling and qualification

The THINS project focuses on crosscutting issues of thermal-hydraulics encountered in innovative nuclear systems. It brings 24 institutions (23 from European Union) together and synergizes infrastructure available in Europe. The overall objectives of the THINS project are the development and validation of new physical models, improvement and qualification of numerical analysis tools and their application to innovative nuclear systems.

Efforts are made to apply the scientific results of this project to education and knowledge-sharing purpose. A large part of the scientific results will have a fundamental relevance in the field of nuclear thermal-hydraulics, nuclear safety and thermal fluid dynamics in general. It is expected that using the results for teaching purposes is highly attractive to strengthen the basis for maintaining and extending know-how in the field.