An experimental investigation of boiling water reactor parallel channel effects during a postulated Loss of Coolant Accident
This thesis describes an experimental study of parallel channel effects (PCE) on the distribution of emergency core spray cooling water in a Boiling Water Nuclear Reactor (BWR) following a postulated design basis Loss Of Coolant Accident (LOCA). The experiments were conducted in a scaled test section in which the reactor coolant was simulated by Freon-114 at conditions similar to those postulated to occur in the reactor vessel shortly after a LOCA. A BWR/4 was simulated by a test section which contained three parallel heated channels to simulate fuel assemblies, a core bypass channel, and a jet pump channel. The test section also included scaled regions to simulate the lower and upper plena, downcomer, and steam separation regions. A scaling analysis was performed to insure simulation of countercurrent flow limiting (CCFL) phenomena and real-time system response. Most of the test section was fabricated from glass pipe to permit flow visualization. Nine transient experiments were conducted at simulated BWR conditions. The lower plenum vaporization rate and heater rod power were parametrically varied, while the core spray flow rate was held constant. During these experiments the flow distributions and heat transfer phenomena were observed and measured.
- OSTI ID:
- 5443823
- Resource Relation:
- Other Information: Thesis (Ph.D.)
- Country of Publication:
- United States
- Language:
- English
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Experimental investigation of boiling-water nuclear-reactor parallel-channel effects during a postulated loss-of-coolant accident
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
FUEL CHANNELS
LOSS OF COOLANT
REACTOR COOLING SYSTEMS
HEAT TRANSFER
HYDRAULICS
COMPUTERIZED SIMULATION
RESEARCH PROGRAMS
ACCIDENTS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
REACTOR ACCIDENTS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTORS
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled