Abstract: To study the performance characteristics of AP type passive nuclear power plant under typical station blackout (SBO) condition, the SBO integral tests were conducted on the Advanced Core-cooling Mechanism Experiment (ACME) facility. The accident sequences and key parameters during SBO tests were investigated. The results show that the ACME SBO tests represent the typical SBO accident progress of AP type passive nuclear power plant. The main sequences and thermal-hydraulic phenomena of ACME SBO tests are consistent with those of pre-analysis, and the test results therefore are as to be expected. The water level in pressurizer is raised by volume change of coolant in reactor coolant system (RCS). However the pressurizer does not overflow during the whole test process. Besides, the power of passive residual heat removal heat exchanger (PRHR HX) and that of decay heat can reach a balance. The core decay heat can be transported effectively and continuously. The initial conditions of core makeup tank (CMT) and in-containment refueling water storage tank (IRWST) play an important role in passive residual heat removal phase of accident progress. When one CMT is failed or the temperature and level of cooling water in IRWST are abnormal, the performance of scaled down passive core cooling system (PXS) still can satisfy the accident acceptance criteria.