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U.S. Department of Energy
Office of Scientific and Technical Information

Boiling water nuclear reactor fuel assembly with cross-flow elimination at upper spacer locations

Patent ·
OSTI ID:7176671
This patent describes a fuel assembly having an array of spaced fuel rods, an outer tubular flow channel surrounding the fuel rods so as to direct flow of coolant/moderator fluid therealong, and a water cross extending through the channel and having radially extending members dividing the array of fuel rods into separate fuel rod mini-bundle subassemblies, each radial member being connected at multiple segments along its outer longitudinal edge to the channel so as to define a series of spaced apart openings between the member and channel which allow cross-flow of coolant/moderator between adjacent subassemblies for pressure equalization therebetween. Each subassembly has spacers being displaced from one another along the length of the subassembly between the bottom and top thereof and surrounding the fuel rods thereof so as to maintain them in side-by-side space relationship. The improvement comprises: means interconnecting the each water cross radial member and the channel for closing predetermined ones of the openings adjacent the locations of upper ones of the spacers for blocking portions of the coolant/moderator cross-flow between the separate mini-bundles via the predetermined ones of the openings so as to minimize degradation of CHF performance and resulting penalties and uncertainties associated therewith. The blocking means are in the form of a solid continuous structure impervious to cross-flow and interconnecting each radial member and the channel adjacent the locations of the upper ones of the spacers.
Assignee:
Westinghouse Electric Corp., Pittsburgh, PA
Patent Number(s):
US 4738819
OSTI ID:
7176671
Country of Publication:
United States
Language:
English