Evaluation of the irradiation behavior of a Zircaloy-4 clad rod containing low density UO/sub 2/ fuel pellets (LWBR Development Program)

Technical Report · Mon Jan 01 04:00:00 EST 1968

OSTI ID:6742243

McCauley, J E; Patterson, P W; Daniel, R C; Meieran, H B

A Zircaloy-4-sheathed, rod type fuel element containing low density (approximately 81.4% of theoretical) UO/sub 2/ fuel pellets was irradiated to a peak average depletion of 13.5 x 10/sup 20/ fissions per cubic centimeter of fully dense fuel at an estimated peak pellet temperature of 2710/sup 0/F. The specimen was removed from the reactor at approximately 50% of design lifetime in order to evaluate the fuel and cladding irradiation-induced changes in the absence of the complicating effects usually associated with in-reactor specimen failure. Extensive dimensional and metallographic evaluation indicated that at that point in lifetime, the fuel swelling was totally accommodated within the void internal to the oxide pellet. Within measurement error, no external dimensional changes were observed that could be related to fuel swelling. Corrosion weight gain and hydrogen uptake in the cladding were in agreement with behavior anticipated from out-of-pile, static autoclave tests. Reasonable agreement was obtained between measurements and calculations of fuel and cladding deformation as a function of irradiation lifetime. These calculations were performed with the analysis method incorporated in the CYGRO-2 digital program. The material properties and other input parameters and assumptions are presented in detail. (NSA 22: 41133)

• Research Organization: Bettis Atomic Power Lab., Pittsburgh, PA (USA)
• DOE Contract Number: AT(11-1)-GEN-14
• OSTI ID: 6742243
• Report Number(s): WAPD-TM-596
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CHALCOGENIDES
DEFORMATION
FUEL ELEMENTS
LWBR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE
RADIATION EFFECTS
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TIN ALLOYS
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URANIUM OXIDES
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ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS