CSNI0055: FIST/6SB1, BWR/6 Simulated Recirculation Line Break

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CSNI0055 FIST/6SB1. (Abstract last modified 18-JAN-1993)

FIST/6SB1, BWR/6 Simulated Recirculation Line Break

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

1. NAME OR DESIGNATION - FIST/6SB1.

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/6SB1 CSNI0055/01 Arrived

Machines used: Package-ID Orig.Computer Test Computer CSNI0055/01 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 - This test simulates a BWR/6 recirculation line break of 0.05 squ.ft. with a stuck open safety relief valve. In addition, similar to test 6SB2C, HPCS is assumed to be unavailable. Test 6SB1 is performed with a BWR/6 core average power of 4.64 MW.
A nominal ADS time delay of 105 seconds is used. ECC water temperature is 120 deg.F. The system pressure does not reach the SRV opening setpoint during the period between MSIV closure and ADS activation.

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
CSNI0055/01: 18-JAN-1993 Arrived at NEADB

10. REFERENCES -
CSNI0055/01:
- 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 - 6SB1.

12. PROGRAMMING LANGUAGE(S) USED -
CSNI0055/01:

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

16. MATERIAL AVAILABLE -
CSNI0055/01:
Directory             (TOTAL: 37.2 MB)
Computed Parameters           12.5 MB
Levels                         2.9 MB
Differential Pressures         7.6 MB
Pressures                      0.7 MB
Powers                         0.3 MB
Rotational Speeds (Pump)       0.2 MB
Temperatures                  12.4 MB
Valve Positions                0.7 MB

17. CATEGORIES -

- Y. Integral Experiments Data, Databases, Benchmarks

Keywords: DATA

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