Hydride damage resistant fuel elements

Induced nuclear reactions: processes – systems – and elements – Fuel component structure – Encased with nonfuel component

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376457, 376417, 376414, G21C 300

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active

054348978

ABSTRACT:
A cladding tube is provided having an axis and a cross-section perpendicular to the axis. The cross-section includes (1) an outer circumferential substrate having an inner surface, (2) a zirconium barrier layer bonded to the inner surface of the outer circumferential substrate, and (3) an inner circumferential liner bonded to the inner surface of the zirconium barrier layer. The inner circumferential liner includes a plurality of facets aligned substantially in parallel with the cladding tube axis. The facets--which define the geometry of the cladding interior--facilitate mixing among the gases in the cladding interior. Also provided is a fuel element including (1) a cladding tube having an faceted inner liner as described above, (2) nuclear fuel material disposed within said cladding tube in a fuel region, and (3) a plenum or plenums located in one or both end regions (beyond the nuclear fuel region) within the cladding tube. In the event of steam entering the cladding interior, the plenum(s) serves as a reservoir making steam available to dilute locally high hydrogen/steam regions. At least a portion of the nuclear fuel is a uranium dioxide having an oxygen to uranium mole ratio in excess of 2.

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Proebstle, R. A.; Davies, J. H.; Rowland. T. C.; Rutkin, D. R.; and Armijo, J. S., "The Mechanism of Defection of Zircaloy-clad Fuel Rods by Internal Hydriding", GE Reference No. NEDO-20684 75NED16 dated, Apr. 1975.
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Mogard, H.; "Suppression of PCI Induced Defects by Lightly Undulating the Bore Surface of the Fuel Cladding," ANS Topical Meeting, St. Charles, Illinois, May 9-11, 1977.
Mogard, H.; Grounes, M.; and Tomani, H., "Irradiation Investigation of the Initial Phase of Degradation of BWR Type Fuel Rodlets containing Simulated Single Fretting Clad Defects", Enlarged Halden Programme Group Meeting, Bolkesjo, Norway, Jun. 9-14, 1991.
Kjaer-Petersen, N.; and Mogard, H., "In-Reactor Performance of Fuel with Rifled Cladding," American Nuclear Society Topical Meeting on LWR Fuel Performance, pp. 284, Williamsburg, Virginia, Apr. 17-20, 1988.

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