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CSNI0045 ROSA-III/984.

ROSA-III/984, BWR Rig of Safety Assessment for LOCA, 2.8% Split Break Test

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1. NAME OR DESIGNATION:  ROSA-III/984.
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2. COMPUTERS
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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.
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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
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM: EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS
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6. PHENOMENA TESTED

Core thermal hydraulics; parallel channel effects and instabilities; void collapse and temperature distribution during pressurization; critical power ratio.
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7. UNUSUAL FEATURES: SPECIAL FEATURES OF EXPERIMENT
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8. COUNTERPART EXPERIMENTS:  FIST
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9. STATUS
Package ID Status date Status
CSNI0045/02 17-SEP-2010 Tested at NEADB
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10. REFERENCES
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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11. TEST DESIGNATION:  984
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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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
CSNI0045/02
Data in ASCII and report
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

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