TEMPERATURE DISTRIBUTION IN UO$sub 2$ FUEL ELEMENTS
Journal Article
·
· Journal of Nuclear Materials (Netherlands)
Evidence is presented that the temperature distribution in fuel elements, in which the UO/sub 2/ is in pressure contact with its sheath, is well- known and predictable. The temperature drops through the fuel itself, across any cracks in the fuel, and across the fuel/sheath interface are discussed. Previous Chalk River results are confirmed and extended without significantly altering any former conclusions. The evidence suggests that only at temperatures below 600 un. Concent 85% C does irradiation significantly decrease the thermal conductivity of UO/sub 2/, up to a burn-up of at least 40,000 Mwd/ton U. Since many of the temperatures in UO/sub 2/ have been deduced from observations on grain growth, some of the factors affecting it were examined; besides the temperature, the time at temperature, the original grain size, and the O: U ratio of the fuel are all important. The data presented permit calculation of the temperature distribution in fuel elements assembled with small diametral clearances. (P.C.H.)
- Research Organization:
- Atomic Energy of Canada Ltd., Chalk River, Ont.
- NSA Number:
- NSA-17-021267
- OSTI ID:
- 4719262
- Journal Information:
- Journal of Nuclear Materials (Netherlands), Journal Name: Journal of Nuclear Materials (Netherlands) Vol. Vol: 7; ISSN JNUMA
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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