Validation of LILAC code for multi-dimensional thermal hydraulics

Heat transfer and fluid flow are one of most important phenomena in nuclear system. Currently numerical simulation method called LILAC to analyse cooling of reactor core molten pool in a lower head vessel is developed. It solves Navier-Stokes equations with turbulence and heat transfer models. The solution domain can be 2-dimensional, axisymmetric and 3-dimensional. LILAC has a capability of multi-layered conjugate heat transfer with melt solidification. The final step of the LILAC code development is analysis of high Rayleigh number natural convection in a stratified molten pool. Before that it is necessary to validate accuracy of the numerical code by solving well known benchmark problems. In this article 13 problems are selected and solved using LILAC code. And the numerical results are compared with experimental data or other computer data. Form this work it is found that LILAC produces numerical solutions accurately and it can be useful for analysis of thermal hydraulics in nuclear engineering