The failure mechanics of high exposure, in-reactor coextruded fuel rods are quite different from those of defected unirradiated rods. The appearance and corrosion behavior of the high-exposure in-reactor failures suggests that the strength of the coextruded Zircaloy-2 to uranium bond has deteriorated. Notch-fracture tests, in which the strength of the Zircaloy-2 clad to uranium bond is evaluated in a qualitative manner, suggests that the bond strength has not deteriorated to the degree indicated by the failure behavior. It is believed that the irradiation induced property changes of the uranium fuel and not a deterioration of the character of the bond …
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Publisher Info:
General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
Place of Publication:
Richland, Washington
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Description
The failure mechanics of high exposure, in-reactor coextruded fuel rods are quite different from those of defected unirradiated rods. The appearance and corrosion behavior of the high-exposure in-reactor failures suggests that the strength of the coextruded Zircaloy-2 to uranium bond has deteriorated. Notch-fracture tests, in which the strength of the Zircaloy-2 clad to uranium bond is evaluated in a qualitative manner, suggests that the bond strength has not deteriorated to the degree indicated by the failure behavior. It is believed that the irradiation induced property changes of the uranium fuel and not a deterioration of the character of the bond are responsible for the difference in irradiated and unirradiated failure behavior.
Physical Description
6 p.
Notes
OSTI as DE94011994; Paper copy available at OSTI: phone, 865-576-8401, or email, reports@adonis.osti.gov
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