Development and Verification of Thermal-Hydraulic Transient Analysis Code in Plate-Type Fuel Nuclear Reactor

The mathematic models for the thermal-hydraulic transient analysis of the plate-type fuel reactor system are established, and a code named SYSTRAN is developed. The design condition of China advanced research reactor (CARR) and the blockage transient case of the IAEA MTR are calculated to verify the SYSTRAN code. Comparison with the flow distribution, outlet temperature etc. obtained by SYSTRAN with the reference parameters indicates that the calculated results agree well with the reference values, which demonstrates that the SYSTRAN code can be used for the thermal-hydraulic analysis in the plate-type fuel reactor system.