Experiment design and scaling analysis for the BWR FIST
Description
The Full Integral Simulation Test (FIST) program is an extension of BWR safety technology into the areas of small break LOCAs and operational transients. To tie back with the existing data base, design basis accident LOCAs will also be performed. The FIST facility is an integral system capable of full power steady state operation and real time simulation of transients, including power excursions and/or degraded systems. It is a full height simulation of the reactor vessel and internals with scaled regional volumes, and includes all major interfacing systems and automatic trip signals. Combined with a full size electrically heated bundle, this provides full scale values for fluid conditions, velocities, and static heads. The program provides data for evaluation of the governing phenomena, for development and qualification of thermal hydraulic methods, and for evaluation of reactor system operating information. Factors considered in the design of the FIST facility include BWR design features important to scaling, the system parameters and phenomena which must be accurately simulated, and experience gained from design of previous scaled facilities
Additional details
Publishing Information
- Imprint Title
- Tenth water reactor safety research information meeting: proceedings. Volume 1
- Journal Page Range
- p. 60-70.
- Report number
- NUREG/CP--0041-Vol.1
Conference
- Title
- 10. water reactor safety research information conference.
- Dates
- 12-15 Oct 1982.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15049696
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; DESIGN BASIS ACCIDENTS; ECCS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PRESSURE VESSELS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR OPERATION; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; SCALE MODELS; SIMULATION; TESTING; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; COOLING SYSTEMS; ENERGY TRANSFER; OPERATION; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; STRUCTURAL MODELS; WATER COOLED REACTORS; WATER MODERATED REACTORS