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아드난 위수다푸트라,서명관,윤병조,정재준 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.3
The MARS code has been assessed for the prediction of onset of flow instability (OFI) in a vertical channel. For assessment, we built an experiment database that consists of experiments under various geometryand thermal-hydraulic condition. It covers pressure from 0.12 to 1.73 MPa; heat flux from 0.67 to3.48 MW/m2; inlet sub-cooling from 39 to 166 C; hydraulic diameters between 2.37 and 6.45 mm ofrectangular channels and pipes. It was shown that the MARS code can predict the OFI mass flux for pipesreasonably well. However, it could not predict the OFI in a rectangular channel well with a mean absolutepercentage error of 8.77%. In the cases of rectangular channels, the error tends to depend on the hydraulicdiameter. Because the OFI is directly related to the subcooled boiling in a flow channel, wesuggest a modified subcooled boiling model for better prediction of OFI in a rectangular channel; the netvapor generation (NVG) model and the modified wall evaporation model were modified so that the effectof hydraulic diameter and heat flux can be accurately considered. The assessment of the modified modelshows the prediction of OFI mass flux for rectangular channels is greatly improved.
Development of a special thermal-hydraulic component model for the core makeup tank
김민기,아드난 위수다푸트라,이종혁,김경두,박현식,정재준 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.5
We have assessed the applicability of the thermal-hydraulic system analysis code, SPACE, to a smallmodular reactor called SMART. For the assessment, the experimental data from a scale-down integraltest facility, SMART-ITL, were used. It was conformed that the SPACE code unrealistically calculates thesafety injection flow rate through the CMT and SIT during a small-break loss-of-coolant experiment. Thisunrealistic behavior was due to the overprediction of interfacial heat transfer at the steam-waterinterface in a vertically stratified flow in the tanks. In this study, a special thermal-hydraulic component model has been developed to realistically calculate the interfacial heat transfer when a strong nonequilibrium two-phase flow is formed in the CMT or SIT. Additionally, we developed a special heatstructure model, which analytically calculates the heat transfer from the hot steam to the cold tank wall. The combination of two models for the tank are called the special component model. We assessed itusing the SMART-ITL passive safety injection system (PSIS) test data. The results showed that the specialcomponent model well predicts the transient behaviors of the CMT and SIT.