[en] Test L2-2 was the first test in the Power Ascension Test Series (Test Series L2) of nuclear full double-ended cold leg break tests conducted by the Loss-of-Fluid Test (LOFT) Program. The specific objectives of Test L2-2 were to determine fuel rod-to-coolant heat transfer in the postcritical heat flux regime and to determine whether any cladding perforation occurs as a result of a 26.25 kW/m maximum linear heat generation rate (50% rated core power). To satisfy these objectives, the LOFT facility was configured to simulate a large (approx. 1000 MWe) pressurized water reactor loss-of-coolant accident resulting from a 200% double-ended offset shear break in the cold leg of the primary coolant system. The initial conditions in the primary coolant system intact loop were: hot leg temperature, 580.4 K; cold leg temperature, 557.7 K; pressure, 15.64 MPa; and intact loop flow, 194.2 kg/s. During system depressurization into a simulated containment, emergency core cooling water was injected into the primary coolant system cold leg to provide data on the effects of emergency core cooling on system thermal-hydraulic response. The experiment was successful in accomplishing these objectives. Recorded data for Test L2-2 are presented