Development of Thermal-Hydraulic Analysis Code for Plate Type Fuel Reactor

Abstract

A multi-channel model thermal-hydraulic analysis code is development for plate type fuel reactor. In this code, every fuel assembly in reactor is divided into a subchannel. A series of reasonable mathematical and physical model are set up based on the structure and operational characteristics of plate type fuel core. As for the choice of flow friction and heat transfer models, all possible flow regimes which include the laminar flow, transient flow and turbulent flow, and heat transfer regimes which include single liquid phase heat transfer, sub-cooled boiling, saturation boiling, film boiling and single vapor phase heat transfer, are considered. The correlations and constitutive equations used in the code are fit for the rectangular channel. Thus the code is suitable for the plate type fuel reactor. By simulating whole reactor of CARR, the detailed flow distribution in each fuel assembly is obtained. The temperature of coolant, quality, void fraction, DNBR in each subchannel is calculated. Point reactor model is introduced in this code. A reactivity insertion accident is simulated in this paper. The results show that the recently developed code is feasible and reliable.