Intermediate flow mixing nonsupport grid for BWR fuel assembly

Patent · Tue Oct 06 04:00:00 EDT 1987

OSTI ID:5779623

Taleyarkhan, R P

An intermediate flow mixing nonsupport grid is described for use in a nuclear reactor fuel assembly containing an array of elongated fuel rods. The grid comprises: (a) interleaved inner straps arranged in an egg-crate configuration to define inner cell openings for receiving respective ones of the fuel rods. The inner straps have outer terminal end portions; (b) an outer peripheral strap attached to the respective terminal end portions of the inner straps to define perimeter cell openings for receiving other ones of the fuel rods. The inner straps and outer strap together have opposite upstream and downstream sides; (c) a first group of mixing vanes disposed at the downstream side and being attached on portions of the outer strap and on respective portions of the inner straps. Together with the outer strap portions, they define the perimeter cell openings. Each of the mixing vanes of the first group extend generally in a downstream direction and inwardly toward the perimeter cell openings for deflecting coolant flowing; and (d) a second group of mixing vanes disposed at the downstream side and being attached on other portions of the inner straps. Together with the respective portions, they define the inner cell openings. Each of the mixing vanes of the second group extend generally in a downstream direction and inwardly toward the inner cell openings for deflecting coolant flowing therethrough; (e) the mixing vanes of the second group are substantially smaller in size than the mixing vanes of the first group so as to generate substantially less turbulence in the portions of the coolant flowing through the inner cell openings than in the portions of the coolant flowing through the perimeter cell openings.

• Assignee: Westinghouse Electric Corp., Pittsburgh, PA
• Patent Number(s): US 4698204
• OSTI ID: 5779623
• 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
COOLANTS
COOLING SYSTEMS
DESIGN
ENERGY SYSTEMS
FINS
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
HYDRODYNAMICS
LIQUID FLOW
MECHANICAL STRUCTURES
MECHANICS
MIXING
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SUPPORTS
WATER COOLED REACTORS
WATER MODERATED REACTORS