Induced nuclear reactions: processes – systems – and elements – Reactor structures – Circulating fluid within reactor
Reexamination Certificate
2006-10-24
2009-12-01
Palabrica, Rick (Department: 3663)
Induced nuclear reactions: processes, systems, and elements
Reactor structures
Circulating fluid within reactor
C376S407000, C376S461000, C411S078000, C403S220000, C292S177000
Reexamination Certificate
active
07627074
ABSTRACT:
A vertical spring wedge restores a tight fitup against an adjacent structure, such as between an inlet mixer and an adjacent restrainer bracket in a boiling water nuclear reactor jet pump. The vertical spring wedge includes a U-shaped bracket including a pair of guiding portions and a pair of bracket holes. A pair of wedge assemblies are coupled with the bracket, each of the wedge assemblies including a wedge segment attached to a spring-loaded guide rod. The guide rods are displaceable in the bracket holes between a retracted position and an extended position. The wedge segments engage the guiding portions, and a combination of the bracket and wedge assemblies have a first width when the guide rods are in the retracted position and have a second width wider than the first width when the guide rods are in the extended position.
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Broaddus Mark William
Erbes John
Tu Thanh C.
General Electric Company
Nixon & Vanderhye P.C.
Palabrica Rick
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