Abstract: LOCUST is a thermo-hydraulic system analysis code developed by China General Nuclear Power Corporation（CGN）. To support the application of LOCUST in analysis such as PWR LOCA accidents, the validation of LOCUST blowdown heat transfer performance against THTF steady experiments, which was conducted by the Oak Ridge National Laboratory, was carried out. The steady film boiling experiments simulated and reported are tests 3.07.9B,3.07.9N, 3.07.9W, 3.07.9H, which cover the test conditions of high and low mass flux and high and low pressure condition. A short introduction of the experiments is given and then the LOCUST input model of the facility is described. Lastly, the calculation results were compared with data followed by a conclusion of the assessment. The overall reasonable prediction of the CHF position and the rod surface temperature shows that LOCUST can be used to simulate blowdown heat transfer of PWR. Small discrepancy of the wall temperature was observed that can be caused by over predicted entrainment or wall heat transfer, which can only be specified by further assessment with measured parameters such as entrainment.