Review of the effects of burnup on the thermal conductivity of UO2
- Author
- Lokken, R. O.
- Published
- United States : [publisher not identified], 1976.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1976. - Physical Description
- microfiche : negative ; 11 x 15 cm
- Additional Creators
- Courtright, E. L.
- Summary
- The general trends which relate changes in thermal conductivity of UO/sub 2/ fuel as a function of temperature and burnup can be summarized as follows: (1) At temperatures below 500/sup 0/C, reductions in UO/sub 2/ thermal conductivity relative to the unirradiated values can be expected up to a saturation level of approximately 10/sup 19/ fissions/cc. (2) At temperatures above 500/sup 0/C, the thermal conductivity will undergo little change at low burnups, (less than 10/sup 19/ fissions/cc) but at higher exposures some decrease can be expected which should, in turn, diminish with increasing temperature. (3) A review of the data reported by Berman on the ThO/sub 2/--UO/sub 2/ fuel indicates that the basic behavior is the same as for UO/sub 2/ in the temperature range of major interest. The applicability of this data to LWR UO/sub 2/ fuel is somewhat questionable because of basic physical property differences, and limited data on irradiation effects, and would not seem to support concerns that the effects of burnup on thermal conductivity for LWR fuel may be of more significance than currently believed. (4) A mathematical expression of the type proposed by Daniel and Cohen seems to provide a reasonable approximation for the behavioral trends reported in the literature which relate changes in thermal conductivity to increasing burnup in certain temperature regimes. Calculations indicate that only small incremental increases in the fuel centerline temperature might be expected if burnup effects are taken into account.
- Report Numbers
- BNWL-2270
- Other Subject(s)
- 050700 - nuclear fuels- fuels production & properties
- 11 nuclear fuel cycle and fuel materials
- 36 materials science
- 360204 - ceramics, cermets, & refractories- physical properties
- Actinide compounds
- Burnup
- Bwr type reactors
- Chalcogenides
- Fuel pellets
- Oxides
- Oxygen compounds
- Pellets
- Physical properties
- Pwr type reactors
- Reactors
- Temperature dependence
- Thermal conductivity
- Thermodynamic properties
- Uranium compounds
- Uranium dioxide
- Uranium oxides
- Water cooled reactors
- Water moderated reactors
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- DOE contract number: EY-76-C-06-1830
OSTI Identifier 7212228
Research organization: Battelle Pacific Northwest Labs., Richland, WA (United States).
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