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[Program Service | Recent programs]

CSNI0056 FIST/6PMC1. (Abstract last modified 18-JAN-1993)


FIST/6PMC1, BWR/6-128 Isolation Valve (MSIV) Closure without Power Scram

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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 - FIST/6PMC1.


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
FIST/6PMC1           CSNI0056/01 Arrived

Machines used:
Package-ID     Orig.Computer                       Test Computer
CSNI0056/01    Many Computers                      

3. DESCRIPTION OF TEST FACILITY - The FIST facility is scaled to a BWR/6-218 standard plant. A full size bundle with electrically heated rods is used to simulate the reactor core. A scaling ratio of 1/624 is applied in the design of the system components. Key features of the FIST facility include: (1) Full height test vessel and internals; (2) correctly scaled fluid volume distribution; (3) simulation of ECCS, S/RV, and ADS; (4) level trip capability; (5) heated feedwater supply system, which provides the capability fo steady state operation.


4. DESCRIPTION OF TEST - Isolation Valve (MSIV) closure without power scram. HPCS and RCIC are assumed to be functional.The power transient test simulation is based on a transient code calculation for a BWR.


5. EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS -


6. PHENOMENA TESTED - distribution; core heat transfer including DNB, dryout, RNB, surface to surface radiation; quench front propagation for both fuel rods and channel walls; separator behaviour including flooding, steam penetration and carryover; phase separation and mixture level behaviour; guide tube and lower plenum flashing; natural circulation in core and downcomer; mixture level in core.


7. SPECIAL FEATURES OF EXPERIMENT -


8. COUNTERPART EXPERIMENTS -


9. STATUS
CSNI0056/01: 18-JAN-1993 Arrived at NEADB


10. REFERENCES  - 
CSNI0056/01:
- W.S. Hwang, Md.Alamgir and W.A. Sutherland:
BWR Full Integral Simulation Test (FIST) Phase I Test Results
NUREG/CR-3711, November 1983
- W.A. Sutherland, Md.Alamgir, J.A. Findlay, W.S. Hwang:
BWR Full Integral Simulation Test (FIST) Phase II Test Results and
TRAC-BWR Model Qualification
NUREG/CR-4128, June 1985


11. TEST DESIGNATION - 6PMC1


12. PROGRAMMING LANGUAGE(S) USED -
CSNI0056/01: 


15. ESTABLISHMENT -
Work sponsored by: U.S. Nuclear Regulatory Commission
                   Electric Power Research Institute
                   General Electric Company


16. MATERIAL AVAILABLE -
CSNI0056/01:
Directory        (TOTAL:   62.0 MB)        
Computed Parameters        24.4 MB         
Flows                       0.5 MB         
Levels                      4.0 MB         
Differential Pressures     10.9 MB         
Pressures                   1.0 MB         
Powers                      0.4 MB         
Rotational Speed (Pump)     0.3 MB         
Temperatures               19.4 MB         
Valve Positions             1.0 MB         


17. CATEGORIES  - 

- Y. Integral Experiments Data, Databases, Benchmarks


Keywords: DATA

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