[en] 1 - Description of test facility: ROSA-III is a 1/124 scaled down test facility with electrically heated core designed to study the response of engineered safety features to loss-of-coolant accidents in in commercial BWR. It consists of the following, fully instrumented subsystems: (a) the pressure vessel with a core simulating four half-length fuel assemblies and control rod; (b) steam line and feed water line, which are independent open loops; (c) coolant recirculation system, which consists of two loops provided with a recirculation pump and two jet pumps in each loop; (d) emergency cooling system, including HPCS, LPCS, LPCI, and ADS. 2 - Description of test: Run 984 simulated a 2.8% split break at the recirculation pump suction line in the broken recirculation loop of a reference BWR. The core power is kept constant for 8 seconds into the break and then reduced along the curve that simulates the surface heat flux of a high power nuclear BWR rod. The feedwater supply is shut off between 2 and 4 seconds after the break. The coolant recirculation pumps are tripped to start coasting down at break initiation