Development and Validation of Thermal-Hydraulic Analysis Code for Plate Type Fuel Research Reactors

A thermal-hydraulic analysis code has been developed with Visual Fortran 6.5 for the investigation of plate type fuel reactors, based on the fundamental conservation of mass, momentum and energy, and some proper constitutive correlations of flow friction factor, heat transfer and property. The Reactivity Insertion Accident（RIA） and Loss Of Flow Accident （LOFA）, which have been defined in the IAEA 10 MW MTR Benchmark transients, were analyzed with this developed program. The comparison of some key parameters, such as the core power at scram, the maximum fuel temperature, the maximum clad temperature and the maximum outlet coolant temperature demonstrated that the results were consistent with that in the literature, which indicated that the model of this developed code is proper for thermal-hydraulic analysis of plate type research reactors.