THE IRRADIATION OF HYDRAULIC RABBIT SPECIMENS TO STUDY SHEATH DEFORMATIONS
Technical Report
·
OSTI ID:4716817
Specimens of UO/sub 2/ sheathed in 0.51 mm aluminum or 0. mm or 0.86 mm stainless steel were irradiated in the Hydraulic Rabbit of NRX to study sheath deformations. Axial expansions were in accordance with a model in which the UO/ sub 2/ is assumed to have a plastic core, sheath expansion being caused by expansion of the innermost non-plastic ring of UO/sub 2/. It was shown that the weaker the sheath the greater is the axial expansion. Diametral expansions increased with increasing specimen heat rating, increasing rapidly at ratings corresponding to the onset of central melting. Volume expansions of the Hydraulic Rabbit specimens were approximately the same as volume expanaions of elements irradiated in pressurized water loops. (auth)
- Research Organization:
- Atomic Energy of Canada Ltd., Chalk River, Ont.
- NSA Number:
- NSA-17-011256
- OSTI ID:
- 4716817
- Report Number(s):
- CRFD-1119; AECL-1664
- Country of Publication:
- Canada
- Language:
- English
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