CSNI0041: ROSA-III/922, BWR Rig of Safety Assessment for LOCA, 5% Split Break Test

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CSNI0041 ROSA-III/922. (Abstract last modified 29-JUN-1992)

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

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

1. NAME OR DESIGNATION - ROSA-III/922.

2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

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Explanation of the status codes.

Program-name Package-ID Status ROSA-III/922 CSNI0041/01 Report

Machines used: Package-ID Orig.Computer Test Computer CSNI0041/01 Many Computers

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.

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.

5. EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS -

6. PHENOMENA TESTED - Core thermal hydraulics; parallel channel effects and instabilities; void collapse and temperature distribution during pressurization; critical power ratio.

7. SPECIAL FEATURES OF EXPERIMENT -

8. COUNTERPART EXPERIMENTS -

9. STATUS
CSNI0041/01: 29-JUN-1992 Report Only

10. REFERENCES -
CSNI0041/01:
- 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

11. TEST DESIGNATION - 922

12. PROGRAMMING LANGUAGE(S) USED -
CSNI0041/01:

15. ESTABLISHMENT -
     Japan Atomic Energy Research Institute
     TOKAI-MURA
     Naka-gun, Ibaraki-ken 319-11
     JAPAN

16. MATERIAL AVAILABLE -
CSNI0041/01:
ROSA-III test report 922

17. CATEGORIES -

- Y. Integral Experiments Data, Databases, Benchmarks

Keywords: DATA, LOSS-OF-COOLANT ACCIDENT, TRANSIENTS

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