Experimental investigation of boiling-water nuclear-reactor parallel-channel effects during a postulated loss-of-coolant accident

Technical Report · Wed Dec 01 00:00:00 EST 1982

DOI:https://doi.org/10.2172/6634845· OSTI ID:6634845

Conlon, W. M.; Lahey, Jr., R. T.

This report describes an experimental study of the influence 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 (LCA). 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 (PCE) 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 inlcuded scaled regions to simulate the lower and upper plena, downcomer, and steam separation regions of a BWR. A series of nine transient experiments were conducted, in which the lower plenum vaporization rate and heater rod power were varied while the core spray flow rate was held constant to simulate that of a BWR/4. During these experiments the flow distribution and heat transfer phenomena were observed and measured.

• Research Organization: Rensselaer Polytechnic Inst., Troy, NY (USA). Dept. of Nuclear Engineering
• OSTI ID: 6634845
• Report Number(s): NUREG/CR-2971; ON: DE83901046
• Resource Relation: Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
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BWR TYPE REACTORS
CORE SPRAY SYSTEMS
LOSS OF COOLANT
HYDRAULICS
HYDRODYNAMICS
TEST FACILITIES
FLOW RATE
MOCKUP
PRESSURE GRADIENTS
REACTOR SAFETY
TEMPERATURE GRADIENTS
ACCIDENTS
ECCS
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
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REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
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STRUCTURAL MODELS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled