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[Program Service | Recent programs]

CSNI0042 ROSA-III/926. (Abstract last modified 29-JUN-1992)


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

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Abstract Table of Contents:

NAME | COMPUTER | PROBLEM | SOLUTION | RESTRICTIONS | CPU | FEATURES | AUXILIARIES | STATUS | REFERENCES | REQUIREMENTS | LANGUAGE | OPERATING SYSTEM | OTHER RESTRICTIONS | AUTHOR | MATERIAL | CATEGORIES |

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1. NAME OR DESIGNATION - ROSA-III/926.


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

To request or retrieve programs click on the one of the active versions below. A password and special authorization is required.

Explanation of the status codes.

Program-name         Package-ID  Status
ROSA-III/926         CSNI0042/01 Report

Machines used:
Package-ID     Orig.Computer                       Test Computer
CSNI0042/01    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 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.


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 - ROSA-III Run 901.


9. STATUS
CSNI0042/01: 29-JUN-1992 Report Only


10. REFERENCES  - 
CSNI0042/01:
- 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.:
ROSA-III 200% Double-ended Break Integral Test Run 926 (HPCS Failure),
JAERI-M 84-008, February 1984


11. TEST DESIGNATION - 926


12. PROGRAMMING LANGUAGE(S) USED -
CSNI0042/01: 


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


16. MATERIAL AVAILABLE -
CSNI0042/01:
Report ROSA-III Test 926                   


17. CATEGORIES  - 

- Y. Integral Experiments Data, Databases, Benchmarks


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

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