CSNI0045 ROSA-III/984.
ROSA-III/984, BWR Rig of Safety Assessment for LOCA, 2.8% Split Break Test
NAME OR DESIGNATION, COMPUTER, DESCRIPTION OF TEST FACILITY, DESCRIPTION OF TEST, RESTRICTIONS, PHENOMENA TESTED, FEATURES, COUNTERPART EXPERIMENTS, STATUS, REFERENCES, TEST DESIGNATION, LANGUAGE, ESTABLISHMENT, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| ROSA-III/984 | CSNI0045/02 | Tested | 17-SEP-2010 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| CSNI0045/02 | Many Computers | PC Windows |
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3. 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.
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.
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4. 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
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
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CSNI0045/02, included references:
- Y. ANODA, K. TASAKA, H. KUMAMARU, M. SHIBA:ROSA-III System Description for Fuel Assembly No. 4, JAERI-M 9363, February 1981
- M. Suzuki et al.:
Recirculation Pump Suction Line 2.8% Break Integral Test at ROSA-III with HPCS
Failure, Run 984, JAERI-M 84-100, June 1984
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Keywords: data, loss-of-coolant accident, transients.