Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
CSNI0041 ROSA-III/922.
last modified: 17-SEP-2010 | catalog | new | search |

CSNI0041 ROSA-III/922.

ROSA-III/922, BWR Rig of Safety Assessment for LOCA, 5% Split Break Test

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1. NAME OR DESIGNATION:  ROSA-III/922.
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2. COMPUTERS
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Program name Package id Status Status date
ROSA-III/922 CSNI0041/02 Tested 17-SEP-2010

Machines used:

Package ID Orig. computer Test computer
CSNI0041/02 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 922 is a LOCA test with a 5% split break at the recirculation pump suction. HPCS was assumed to have failed. Initial conditions of the test were as follows: steam dome pressure 7.35 MPa; lower plenum temperature 552.6 K; core inlet flow rate 16.0 kg/s; core heat generation rate 3.96 MW. Core power before break initiation was maintained at 44% of the scaled steady-state power and then reduced along the decay curve that simulates the total heat transfer rate. The test was terminated, when the entire core was quenched.
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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. RELATED OR AUXILIARY PROGRAMS: COUNTERPART EXPERIMENTS
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9. STATUS
Package ID Status date Status
CSNI0041/02 17-SEP-2010 Tested at NEADB
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10. REFERENCES
CSNI0041/02, included references:
- Y. ANODA, K. TASAKA, H. KUMAMARU, M. SHIBA:
ROSA-III System Description for Fuel Assembly No. 4, JAERI-M 9363, February 1981
- H. Nakamura et al.:
Recirculation Pump Suction Line 5% Split Break Loca Test of ROSA-III (Runs 922
and 932 with HPCS Failure), JAERI-M 85-128, September 1985
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11. TEST DESIGNATION:  922
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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
CSNI0041/02
Data in ASCII and report
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

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