Orificing of water cross inlet in BWR fuel assembly

Patent · Tue Jun 28 04:00:00 EDT 1988

OSTI ID:6878301

Taleyarkhan, R P; Mildrum, C M

A nuclear reactor fuel assembly is described comprising a bundle of elongated fuel rods disposed in side-by-side relationship so as to form an array of spaced fuel rods, a tubular flow channel member surrounding the fuel rods so as to direct flow of coolant/moderator fluid along the fuel rods, respective upper and lower tie plates at opposite ends of the fuel rods, and a hollow water cross having confronting side walls and a closed lower end wall at an inlet end. The water cross extends centrally through and disposed within the flow channel member so as to provide within the flow channel member separate compartments and to divide the bundle of fuel rods into mini-bundles being disposed in the respective compartments, the water cross including inlet cross flow means formed in the side walls near a lower end of the water cross above the closed end wall and near lower end portions of each of the mini-bundles of fuel rods, which inlet cross flow means provides both selected flow communication into the interior of the water cross and flow communication between the respective mini-bundles for minimizing maldistribution and equalizing flow.

• Assignee: Westinghouse Electric Corp., Pittsburgh, PA
• Patent Number(s): US 4753774
• OSTI ID: 6878301
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
COOLING
COOLING SYSTEMS
ENERGY SYSTEMS
FLUID FLOW
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENTS
FUEL RODS
HYDROGEN COMPOUNDS
LIQUID FLOW
OPENINGS
ORIFICES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
ROD BUNDLES
SPACERS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS