Passive Direct Reactor Axiliary Cooling System (DRACS) of China Experimental Fast Reactor (CEFR) can effectively remove decay heat generated by core to protect the reactor safety under accident conditions. To investigate the operation of DHRS under accident conditions, part of scholars have developed one-dimensional system analysis codes by simplifying the effect of fluid in the pool. However, during actual operation, heat is also exchanged between hot liquid sodium in the CEFR pool and liquid sodium in the Direct Heat Exchanger (DHX) cylinder cooled by the DRACS intermediate circuit. In comparison with the actual value, the heat exchanger outlet temperature calculated by the system analysis code is not accurate enough because it doesn’t take into account the heat exchange effect in the pool. In this work, the one-dimensional system analysis code System Analysis Code-passive Direct Reactor Axiliary Cooling System (SAC-DRACS), which has been developed in our research team for simulating the DRACS of CEFR, is improved. The heat transfer model between liquid sodium in the DHX cylinder and hot sodium in the pool is added to the original one. The operation of DRACS under SBO accident was simulated using SAC-DRACS, SAC-DRACS-II and CFD software ANSYS FLUENT, respectively. By comparing the calculation results of SAC-DRACS-II, SAC-DRACS and FLUENT, the validity of the added heat transfer model in the SAC-DRACS-II and the accuracy of the SAC-DRACS-II are verified. The SAC-DRACS-II in this work can be used to couple with FLUENT to calculate the emergency response of CEFR between circuits under an accident. The SAC-DRACS-II in this work can be used for the safety analysis of pool-type fast reactor DRACS.

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