CSNI0054: FIST/6MSB1, BWR/6 Main Steamline Double-Ended Break Test

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

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CSNI0054 FIST/6MSB1. (Abstract last modified 18-JAN-1993)

FIST/6MSB1, BWR/6 Main Steamline Double-Ended Break Test

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

1. NAME OR DESIGNATION - FIST/6MSB1

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/6MSB1 CSNI0054/01 Arrived

Machines used: Package-ID Orig.Computer Test Computer CSNI0054/01 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 for steady state operation.

4. DESCRIPTION OF TEST - The main steamline break test 6MSB1 simulates a BWR/6 response with a double ended break upstream of the flow limiter in one of the four main steamlines. The effective break area consists of one main steamline flow area and one steam line flow limiter, due to back flow via the bypass header. The turbine bypass opens at about 1 second and the effective break flow area at this time also includes the bypass line area. By about 5.5 seconds, the main steam isolation valve is closed and the break is limited to one main steamline. For simplifying the test operation, and having a bounding simulation, the test was performed with full turbine bypass flow are from 0 to 5.5 seconds and one steamline flow area beyond 5.5 seconds.

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
CSNI0054/01: 18-JAN-1993 Arrived at NEADB

10. REFERENCES -
CSNI0054/01:
- W.S. Hwang, Md.Alamgir and W.A. Sutherland:
BWR Fulle 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 - 6MSB1

12. PROGRAMMING LANGUAGE(S) USED -
CSNI0054/01:

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

16. MATERIAL AVAILABLE -
CSNI0054/01:
Directory                    33.2 MB
Computed Parameters          13.5 MB
Levels                        2.1 MB
Differential Pressures        6.2 MB
Pressures                     0.6 MB
Powers                        0.2 MB
Rotational Speeds (Pump)      0.2 MB
Temperatures                  9.8 MB
Valve Positions               0.5 MB

17. CATEGORIES -

- Y. Integral Experiments Data, Databases, Benchmarks

Keywords: DATA

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