Void plug for annular fuel pellets

Patent · Tue Aug 01 04:00:00 EDT 1989

OSTI ID:5274117

Pettus, W G

This patent describes an improved pressurized water reactor nuclear fuel rod. The rod comprising, in combination, a gas-tight outer tubular cladding made of zircaloy, a plurality of annular fuel pellets axially stacked within the cladding. Each of the fuel pellets consisting essentially of uncoated and unencased uranium dioxide, wherein each of the fuel pellets has a cylindrical outer surface in contact with the cladding and a cylindrical inner surface defining a portion of the continuous central cavity extending axially along the center of the fuel rod, a porous void plug inserted within the substantially filling the central cavity. The porous void plug having a transverse thickness perpendicular to the axis of the cladding substantially equal to the inner diameter of the fuel pellets and pressing upon the inner surface of the fuel pellets so as to exert sufficient pressure against the fuel pellets to prevent the breaking away and the relocation of fuel fragments from the fuel pellets. The porous void plug being a compacted porous refractory fiber material operative as a getter for fission product gases and providing means for distributing burnable poisons within the cladding.

• Assignee: Babcock and Wilcox Co., New Orleans, LA
• Patent Number(s): US 4853177
• Application Number: PPN: US 7-053560A
• OSTI ID: 5274117
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ALLOYS
CLADDING
CLOSURES
DEPOSITION
DESIGN
FUEL ELEMENTS
FUEL PELLETS
FUEL RODS
PELLETS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
REFRACTORIES
SURFACE COATING
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS