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CSNI0073 ROSA-IV/SB-CL-27.

ROSA-IV/SB-CL-27, Large Scale Test Facility, Gravity-Driven Safety Injection

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1. NAME OR DESIGNATION:  ROSA-IV/SB-CL-27.
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2. COMPUTERS
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Program name Package id Status Status date
ROSA-IV/SB-CL-27 CSNI0073/02 Tested 17-NOV-2010

Machines used:

Package ID Orig. computer Test computer
CSNI0073/02 Many Computers PC Windows
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3. DESCRIPTION OF TEST FACILITY

Large Scale Test Facility (LSTF) is a 1/48 volumetrically scaled, full-height, full-pressure full-pressure simulator of a Westinghouse-type 4-loop (3423 MWt) PWR. LSTF was used to conduct integral experiments on PWR small break loss-of-coolant accident and operational transients as part of the Rig-of-Safety-Assessment No. 4 (ROSA-IV). 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-27 simulated thermal-hydraulic behavior of a gravity-driven, passive safety injection system during a small-break loss-of-coolant accident (LOCA) in a PWR. The injection system consisted of a gravity-driven injection tank, located above the reactor vessel, with connecting lines. The tank was initially filled with water of room temperature at the same pressure as the pressurizer. The connecting lines to the cold leg and to the vessel downcomer were opened at the test initiation. Then, a natural circulation flow developed in the loop which was formed by these lines and the injection tank. The hot water in the cold leg circulated into the upper part of tank and accumulated there causing a significant thermal stratification. This thermal stratification prevented direct-contact condensation of steam from occurring during the subsequent tank drain-down phase. Therefore, no condensation-induced depressurization of the tank, affecting adversely the injection performance, occurred.
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5. EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS

The passive injection system represented in this test consisted of a water tank located above the reactor vessel and lines for water injection and pressure balancing. This concept resembles the core makeup tank (CMT) in the Westinghouse AP600 design. However, the system test configuration and operational setpoints in this experiment differed much from those for the AP600 design. The present experimental results are not believed to be representative of the AP600 responses.
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6. PHENOMENA TESTED

The included report presents all the experimental data taken for Run SB-CL-27, describes the test initial and boundary conditions, the test configuration and the test procedures. It also summarizes major observations from the test. Data plots for all the instrumentation channels are presented.
  
More than 2300 transducers were used for measurement of thermal-hydraulic parameters during the test. About 70% of these transducers were thermocouples for measurement of fluid and solid wall temperatures as well as differential temperatures. About 400 conduction probes were used to detect the presence of liquid at various locations in the vessel and loops. Other conventional instruments included measurement of pressures, differential pressures, collapsed liquid level based on differential pressure measurements, and flowrates based on differential pressure measurements across orifices or nozzles. In addition, measurements were made using more or less advanced two-phase flow instruments including gamma-ray densitometers and drag discs. Visual observation of the flow in the primary loops was also made using high-pressure video probes located at the inlet and outlet legs of the two SGs.
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7. UNUSUAL FEATURES: SPECIAL FEATURES OF EXPERIMENT
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8. RELATED OR AUXILIARY PROGRAMS: COUNTERPART EXPERIMENTS
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9. STATUS
Package ID Status date Status
CSNI0073/02 17-NOV-2010 Tested at NEADB
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10. REFERENCES
CSNI0073/02, included references:
- Y. Kukita et al.:
Data Report for ROSA-IV LSTF Gravity-Driven Safety Injection Experiment
Run SB-Cl-27 (JAERI-M 94-069, March 1994)
- 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
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11. TEST DESIGNATION:  SB-CL-27
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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15. ESTABLISHMENT

     Japan Atomic Energy Research Institute
     TOKAI-MURA
     Naka-gun, Ibaraki-ken 319-11
     JAPAN
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16. MATERIAL AVAILABLE
CSNI0073/02
Data in binary form, program to convert the data binary into ASCII
report
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: data, loss-of-coolant accident, transients.