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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.
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.
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.
- 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