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CSNI0042 ROSA-III/926.

ROSA-III/926, BWR Rig of Safety Assessment for LOCA, 20% Double-Ended Break

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1. NAME OR DESIGNATION:  ROSA-III/926.
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2. COMPUTERS
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Program name Package id Status Status date
ROSA-III/926 CSNI0042/02 Tested 17-SEP-2010

Machines used:

Package ID Orig. computer Test computer
CSNI0042/02 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 926 simulates a 200% double-ended break in the recirculation line with failure of HPCS. Initial conditions of the test were as follows: steam dome pressure 7.37 MPa; lower plenum temperature 553 K; core inlet flow rate 16.3 kg/s; core power before break initiation 3.967 MW. During the transient, the power was changed along the curve which simulates the total heat transfer rate in the core of the reference BWR.
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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:  ROSA-III Run 901.
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9. STATUS
Package ID Status date Status
CSNI0042/02 17-SEP-2010 Tested at NEADB
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10. REFERENCES
CSNI0042/02, 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.:
ROSA-III 200% Double-ended Break Integral Test Run 926 (HPCS Failure), JAERI-M
84-008, February 1984
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11. TEST DESIGNATION:  926
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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
CSNI0042/02
Data in ASCII and report
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

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