Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

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

Similar Records

STABILITY OF UO$sub 2$-NaK SLURRIES. Final Report
Technical Report · Mon Mar 28 23:00:00 EST 1960 · OSTI ID:4692608

A COLLAPSE MODE OF FAILURE IN POWDER-FILLED FUEL ELEMENTS
Technical Report · Tue Jan 14 23:00:00 EST 1964 · OSTI ID:4007844

The Relative Axial Expansions Under Irradiation Of Stacks Of UO$sub 2$ Pellets In Zircaloy Sheaths
Technical Report · Wed Aug 15 00:00:00 EDT 1962 · OSTI ID:4775263