UO$sub 2$ IRRADIATIONS OF SHORT DURATION. PART II

Technical Report · Wed Feb 01 04:00:00 EST 1961

OSTI ID:4017125

Bain, A S; Robertson, J A.L.; Ridal, A

A description is given of the irradiation of fuel specimens in the "Hydraulic Rabbit'' of the NRX Reactor. It was deduced that the surface temperature of the fuel increased with increasing diametral clearance on the original assembly. For the particular conditions studied, the effect only became appreciable for an original clearance equal to 1% of the diameter, but then increased rapidly. Under the same conditions the substitution of helium for argon as filling gas had a relatively small effect (about 50 deg C) on the fuel surface temperature. In both dismetral and axial directions the sum of the original clearance and the residual sheath strain is, to a first approximation, constaint. Axial expansion of the sheath is decreased by the provision of distributed clearance in the form of dishing of the pellet end faces; the profile of the dishing has a significant effect. The effects of diametral clearance on axial expansion, and vice versa, as well as heat rating and sheath strength on the sheath strains were examined and discussed. (auth)

• Research Organization: Atomic Energy of Canada Ltd. Chalk River Project, Chalk River, Ont.
• NSA Number: NSA-15-017365
• OSTI ID: 4017125
• Report Number(s): CRFD-955; AECL-1192
• Country of Publication: Canada
• Language: English

Related Subjects

ARGON
CONFIGURATION
DEFORMATION
DISTRIBUTION
EXPANSION
FUEL CANS
FUEL ELEMENTS
HEATING
HELIUM
INERT GASES
IRRADIATION
MATERIALS TESTING
METALS, CERAMICS, AND OTHER MATERIALS
PELLETS
RADIATION EFFECTS
REACTORS
SURFACES
TEMPERATURE
URANIUM DIOXIDE