CSNI0057 FIST/6IB1.

1. NAME OR DESIGNATION:  FIST/6IB1.

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 fo steady state operation.

4. DESCRIPTION OF TEST

Test 6IB1 investigates system responses to an intermediate break in the recirculation suction line. BWR system licensing evaluations for various size recirculation break LOCA's indicates that a break size of about 0.2 sq.ft., without LPCS operation, is the highest PCT case for the intermediate break LOCA. Test 6IB1 simulates this event.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM: 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. UNUSUAL FEATURES: SPECIAL FEATURES OF EXPERIMENT

8. RELATED OR AUXILIARY PROGRAMS: COUNTERPART EXPERIMENTS

- A. G. Stephens:
BWR Full Integral Simulation Test (FIST) Program Facility Description Report
NUREG/CR-2576 December, 1982
- 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
- Jae H. Jo and H. Connell:
Simulation of FIST Tests using TRAC-BD1/MOD1
BNL-NUREG--37616, Paper submitted to the ANS Annual Meeting Reno, NV, June
15-19, 1986

11. TEST DESIGNATION:  6IB1

15. ESTABLISHMENT

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

CCVM data        mag tapeDirectory        (TOTAL:  175.1 MB)        CVMTP
CCVM data        mag tapeCurrents                    0.3 MB         CVMTP
CCVM data        mag tapeDensities                   0.5 MB         CVMTP
CCVM data        mag tapeFlows                       0.5 MB         CVMTP
CCVM data        mag tapeLevels                      4.8 MB         CVMTP
CCVM data        mag tapeDifferential Pressures     14.4 MB         CVMTP
CCVM data        mag tapePressures                   1.4 MB         CVMTP
CCVM data        mag tapePowers                      1.7 MB         CVMTP
CCVM data        mag tapeRotational Soeed (Pump)     0.3 MB         CVMTP
CCVM data        mag tapeTemperatures               24.4 MB         CVMTP
CCVM data        mag tapeVoltages                    2.0 MB         CVMTP
CCVM data        mag tapeComputed Parameters       124.6 MB         CVMTP