CSNI0058: FIST/4DBA1, BWR/4-218 Simulated Double-Ended Large Break Test

OECD Nuclear Energy Agency / L'Agence pour l'énergie nucléaire

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CSNI0058 FIST/4DBA1. (Abstract last modified 18-JAN-1993)

FIST/4DBA1, BWR/4-218 Simulated Double-Ended Large Break Test

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

1. NAME OR DESIGNATION - FIST/4DBA1.

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/4DBA1 CSNI0058/01 Arrived

Machines used: Package-ID Orig.Computer Test Computer CSNI0058/01 Many Computers

3. DESCRIPTION OF TEST FACILITY - 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 for steady state operation.

4. DESCRIPTION OF TEST - 4DBA1 simulates conditions in the peak power bundle of BWR/4-218 after a double-ended large break in one of the recirculation suction lines. The BWR/4 break size is much larger than the corresponding BWR/6 break. The scaled break sizes are 1.05 sq.in. in the suction line and 0.1645 sq.in. at the drive line nozzle based on the single bundle FIST scaling. The initial power of 6.09 MW simulates a peak power bundle.

5. EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS -

6. PHENOMENA TESTED - Channel and bypass axial flow and void 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
CSNI0058/01: 18-JAN-1993 Arrived at NEADB

10. REFERENCES -
CSNI0058/01:
- 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 - 4DBA1

12. PROGRAMMING LANGUAGE(S) USED -
CSNI0058/01:

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

16. MATERIAL AVAILABLE -
CSNI0058/01:
Directory      (Total:  120.2 MB)
Currents                  0.3 MB
Computed Parameters      77.1 MB
Densities                 0.5 MB
Flows                     0.5 MB
Levels                    4.1 MB
Differential Pressures   12.3 MB
Pressures                 1.2 MB
Powers                    1.5 MB
Rotational Speeds (Pump)  0.3 MB
Temperatures             20.8 MB
Valve Positions           1.7 MB

17. CATEGORIES -

- Y. Integral Experiments Data, Databases, Benchmarks

Keywords: DATA

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