CSNI0047 ROSA-III/923.

ROSA-III/923, BWR Rig of Safety Assessment for LOCA

NAME OR DESIGNATION, COMPUTER, DESCRIPTION OF TEST FACILITY, SOLUTION, RESTRICTIONS, PHENOMENA TESTED, FEATURES, AUXILIARIES, STATUS, REFERENCES, TEST DESIGNATION, LANGUAGE, ESTABLISHMENT, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION: ROSA-III/923.

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2. COMPUTERS

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Program name	Package id	Status	Status date
ROSA-III/923	CSNI0047/01	Report	12-JAN-1993

Machines used:

Package ID	Orig. computer	Test computer
CSNI0047/01	Many Computers

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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. METHODS: DESCRIPTION OF TEST

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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
CSNI0047/01	12-JAN-1993	Report Only

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10. REFERENCES

CSNI0047/01, included references:

- Mitsuhiro SUZUKI et al.: BWR LOCA Integral Test Simulating A 100% Main Steam
Line Break outside Reactor Containment Vessel in Rosa-III Program, Run 955
Analogy of Steam Line Break and Recirculation Line Small Break, JAERI-M 87-044
March 1987
- Y. ANODA, K. TASAKA, H. KUMAMARU, M. SHIBA:
ROSA-III System Description for Fuel Assembly No. 4, JAERI-M 9363, February 1981

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11. TEST DESIGNATION: 923

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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

CSNI0047/01

ROSA-III report test 923

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