Preliminary Simulation of PAFS Using the CUPID Code

A three-dimensional thermal-hydraulics code, CUPID (Component Unstructured Program for Interfacial Dynamics), is being developed by KAERI (Korea Atomic Energy Research Institute) for the component scale analyses of a reactor coolant system. The CUPID based on a two-fluid three-field model is consisted of the unstructured FVM (Finite Volume Method). The CUPID project was initiated by the requirement of a sophisticated three-dimensional thermal-hydraulics code due to recent developments of nuclear reactors. For example, the downcomer boiling of the DVI (Direct Vessel Injection) system or the acceleration of the two phase natural convection of PAFS (Passive Auxiliary Feed water System) involving extreme phase transition demands high accuracy multidimensional analysis techniques. In this paper, we have analyzed PASCAL model in KAERI as a preliminary simulation using the CUPID