Steam generator simulation model for LMFBR type nuclear power plants

A digital computer (GVST) code was developed to simulate steady-state thermohydraulics of LMFBR s sodium-heated steam generators of the Shell-and-tube type. In a detailed modelling, the steam generator was divided into six heat transfer regions. Depending upon the local conditions of the flow, the heat transfer correlations were selected using adequate criteria. The fluid flow is described by linearized conservation equations in one dimension. An adequate mathematical model, established to simulate transients may be coupled to the code. The results presented are the distributions of temperatures, pressures, and water flow rate, and evaporation and superheater heat transfer lengths. The simplified model neglected slip fraction between water and steam velocities due to the high pressure operation and low pressure drop. (author)