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[Program Service | Recent programs]

CSNI0047 ROSA-III/923. (Abstract last modified 12-JAN-1993)


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

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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/923.


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/923         CSNI0047/01 Arrived

Machines used:
Package-ID     Orig.Computer                       Test Computer
CSNI0047/01    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 -


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
CSNI0047/01: 12-JAN-1993 Arrived, no report


10. REFERENCES  - 
CSNI0047/01:
- Y. ANODA, K. TASAKA, H. KUMAMARU, M. SHIBA:
ROSA-III System Description for Fuel Assembly No. 4
JAERI-M 9363, February 1981


11. TEST DESIGNATION - 923


12. PROGRAMMING LANGUAGE(S) USED -
CSNI0047/01: 


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


16. MATERIAL AVAILABLE -
CSNI0047/01:
ROSA-III report test 923                   


17. CATEGORIES  - 

- Y. Integral Experiments Data, Databases, Benchmarks


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

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