CSNI0043: ROSA-III/952, BWR Rig of Safety Assessment for LOCA, Reference MSL Break Test

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CSNI0043 ROSA-III/952. (Abstract last modified 29-JUN-1992)

ROSA-III/952, BWR Rig of Safety Assessment for LOCA, Reference MSL Break Test

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

1. NAME OR DESIGNATION - ROSA-III/952.

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/952 CSNI0043/01 Report

Machines used: Package-ID Orig.Computer Test Computer CSNI0043/01 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 952 is a reference MSL break test
performed with a 100% break upstream of the main steam isolation
valve and with full ECCS actuation logic. The MSL break is
characterized by a system depressurization due to a break flow of
high mass quality, which is slower than with a recirculation line
break. Continuous flashing of the fluid in the pressure vessel was
observed. A slow decrease in the downcomer water level eventually
led to actuation of HPCS, but not LPCS or LPCI. About 2/3 of the
core was uncovered, but the coolant level recovered quickly
following HPCS injection. A peak cladding temperature of 752K was
reached.

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
CSNI0043/01: 29-JUN-1992 Report Only

10. REFERENCES -
CSNI0043/01:
- Y. ANODA, K. TASAKA, H. KUMAMARU, M. SHIBA:
ROSA-III System Description for Fuel Assembly No. 4
JAERI-M 9363, February 1981
- M. Kawaji et al.:
A Main Steam Line Break Experiment at ROSA-III Run 952 (Standart Run with
full ECCS), JAERI-M 84-229, December 1984

11. TEST DESIGNATION - 952

12. PROGRAMMING LANGUAGE(S) USED -
CSNI0043/01:

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

16. MATERIAL AVAILABLE -
CSNI0043/01:
Report ROSA-III Test 952

17. CATEGORIES -

- Y. Integral Experiments Data, Databases, Benchmarks

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

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