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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 for steady state operation.
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.
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 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