CSNI0046 ROSA-IV/SB-CL-18.
ROSA-IV/SB-CL-18, Large Scale Test Facility, 5% Cold-Leg Break Test
NAME OR DESIGNATION, COMPUTER, DESCRIPTION OF TEST FACILITY, DESCRIPTION OF TEST, RESTRICTIONS, CPU, FEATURES, AUXILIARIES, STATUS, REFERENCES, TEST DESIGNATION, LANGUAGE, ESTABLISHMENT, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| ROSA-IV/SB-CL-18 | CSNI0046/02 | Tested | 17-NOV-2010 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| CSNI0046/02 | Many Computers | PC Windows |
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3. DESCRIPTION OF TEST FACILITY
ROSA-IV is a large scale test facility (LSTF) for integral simulation of thermal-hydraulic response of a pressurized water reactor during a small break
loss-of-coolant accident or an operational transient. The facility has electric core heating. The overall scaling factor is 1/48. The hot and cold legs were sized to conserve the volume scaling. The four primary loops of the reference PWR are represented by two equal-volume loops.
ROSA-IV is a large scale test facility (LSTF) for integral simulation of thermal-hydraulic response of a pressurized water reactor during a small break
loss-of-coolant accident or an operational transient. The facility has electric core heating. The overall scaling factor is 1/48. The hot and cold legs were sized to conserve the volume scaling. The four primary loops of the reference PWR are represented by two equal-volume loops.
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4. DESCRIPTION OF TEST
SB-CL-18 was a 5% cold leg break test. Both the initial steady-state conditions and the test procedures were designed to minimize the effects of scaling compromises. 10 seconds into the break, the turbine throttle valve was closed at a pressurizer pressure of 12.97 MPa. The turbine bypass was inactive, since loss-of-offsite power was assumed concurrently with the scram. The reactor coolant pumps stopped at 265 seconds. The core was uncovered between 120 seconds and 155 seconds into the break.
SB-CL-18 was a 5% cold leg break test. Both the initial steady-state conditions and the test procedures were designed to minimize the effects of scaling compromises. 10 seconds into the break, the turbine throttle valve was closed at a pressurizer pressure of 12.97 MPa. The turbine bypass was inactive, since loss-of-offsite power was assumed concurrently with the scram. The reactor coolant pumps stopped at 265 seconds. The core was uncovered between 120 seconds and 155 seconds into the break.
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CSNI0046/02, included references:
- Y. Kukita et al.:ISP-26 OECD/NEA/CSNI International Standard Problem No.26
ROSA-IV LSTF Cold-Leg Small-Break LOCA Experiment
Comparison Report NEA/CSNI/R(91)13 (February 1992)
- The ROSA-IV Group
"ROSA-IV Large Scale Test Facility (LSTF) - System Description"
JAERI-M 84-237,January 1985
- The ROSA-IV Group
"Supplemental Description of ROSA-IV/LSTF with No. 1 Simulated Fuel-Rod
Assembly", JAERI-M 89-113, September 1989
- H. Kumamaru et al.:
ROSA-IV/LSTF 5% Cold Leg Break LOCA Experiment Run SB-CL-18 Data Report
JAERI-M 89-027 (March 89)
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CSNI0046/02
Data in binary form, program to convert the data binary into ASCIIreport
Keywords: data, loss-of-coolant accident, transients.