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CSNI0039 ROSA-III/912.

ROSA-III/912, BWR Rig of Safety Assessment for LOCA, 5% Split Break Test

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1. NAME OR DESIGNATION:  ROSA-III/912.
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2. COMPUTERS
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Program name Package id Status Status date
ROSA-III/912 CSNI0039/02 Tested 17-SEP-2010

Machines used:

Package ID Orig. computer Test computer
CSNI0039/02 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

This is one of the small break LOCA/ECC test series to study the response of a BWR with ECC injection. Run 912 is a 5% split break test at the recirculation pump inlet. The test is initiated with the steam dome pressure at 7.30 MPa, the lower plenum subcooling at 10.8 K, a core inlet flow rate of 16.4 kg/s, and a core heat generation rate of 3.9 MW. The core is quenched after ECCS actuation and at a maximum fuel cladding temperature of 839 K.
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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
CSNI0039/02 17-SEP-2010 Tested at NEADB
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10. REFERENCES
CSNI0039/02, included references:
- Y. Anoda et al.:
Experiment Data of Rosa-III Integral Test Run 912 (5% Split Break Test
without HPCS Actuation), JAERI-M 82-010, March 1982
- Y. ANODA, K. TASAKA, H. KUMAMARU, M. SHIBA:
ROSA-III System Description for Fuel Assembly No. 4 (JAERI-M 9363, Feb. 1981)
- K. Tasaka et al.:
Comparison Report for CSNI International Standard Problem 12 (ROSA-III
Run 912), JAERI-M 82-120 (September 1982) also NEA/CSNI-100
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11. TEST DESIGNATION:  912
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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
CSNI0039/02
Data in ASCII and report
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

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