Abstract: Based on accident analysis code SAC-CFR, EBR-Ⅱ shutdown heat removal tests (SHRT-17, SHRT-45R) were analyzed in the framework of International Atomic Energy Agency Coordinated Research Project (IAEA CRP) in this paper. The key parameters such as direct reactor auxiliary cooling system (DRACS) response, decay heat power, coolant temperature of key components and mass flow rate in primary loop were calculated. The calculated parameters were compared with measured data, and the effectiveness of the new coupled SAC-CFR code was verified. The results show that each direct heat exchanger (DHX) can remove core decay heat 330 406.4 W with opening of DRACS air damper under SHRT-17 condition. DRACS has capacity of cooling reactor core for long term under natural circulation.