[en] Two Anticipated Transient Without Scram (ATWS) experiments Experiments L9-3 and L9-4, were conducted in the Loss-of-Fluid Test (LOFT) pressurized water reactor (PWR). Experiment L9-3 simulated a loss-of-feedwater ATWS in a commercial PWR and Experiment L9-4 simulated a loss-of-offsite power ATWS. The system transient behavior in each experiment was dominated by interaction between the primary-to-secondary heat removal rate in the steam generator and reactor kinetics in the core. The results of the experiments showed that ATWS events can be controlled by properly sized automatic safety systems and that plant recovery can be accomplished (without inserting the control rods) with recovery procedures involving power-operated relief valve (PORV) cycling, secondary system feed and bleed, and boron injection. The system transient response predicted by the RELAP5/MOD1 computer code showed good agreement with the experimental data